IAEA Nuclear Data Section
|
Evaluated Libraries |
Legend Compilation by V. Piksaikin, A.S. Egorov, D.E. Gremyachkin, K.V. Mitrofanov * Recommended experimental values FSCSW = Fission spectrum. cross section weighted TDN yield = total delayed neutron yield (νd) = average number of delayed neutrons per fission () β = delayed neutron fraction. Yf(235U) = total delayed neutron yield from fast neutron induced fission of 235U. Yt(235) = total delayed neutron yield from thermal neutron induced fission of 235U. Y15(X) = total delayed neutron yield from fission of nucleus X by 15 MeV neutrons σf = fission cross section. <ν> = average number of prompt neutrons. (a) = delayed neutrons per atom/100 incident neutrons (see R.J. Tuttles comments). |
Previous compilations
R.J. Tuttle, Review of delayed neutron yields in nuclear fission, Procedings of the consultants' meeting on delayed neutron properties, report IAEA, indc-107/G, 1979
S. A. Cox, Delayed Neutron Data - Review and Evaluation, ANL/NDM-5, Argonne National Laboratory, 1974 Yu.S. Zamyatnin , V.M. Gorbachev ., A.A. Lbov, Interaction of the radiation with heavy nuclei and nuclear fission. Handbook, Moscow, Atomizdat, 1976 |
# | Target | Energy [MeV] | Total delayed neutron yield | Adjustment basis | Reference | |
---|---|---|---|---|---|---|
Reported | Adjusted | |||||
209-Bi | Charged - Particle induced fission | |||||
1 | 209-Bi | 29.1 (He-3) | 0.0009 ± .0001mb | Reported by: E. T. Chulick and P. l. Reeder, Nucl. Phys, A173, 497, 1971. | ||
2 | 209-Bi | 33.7 (He-3) | 0.0172 ± .0024mb | |||
231-Pa | Neutron induced fission | |||||
3 | 231-Pa | 14.8 | 0.0060 ± 25% | 0.0080 ± .0026 | Reported by: Brown M.G. et al., Radiochem. Acta, 1971, Bd 15, S. 109. Adjusted by: R.J. Tuttle, 1979. | |
4 | 231-Pa * | fast | (0.0111 ± 0.0011) | Recommended by: R.J. Tuttle, 1979. (Value is influenced by empirical estimates). | ||
232-Th | Neutron induced fission | |||||
5 | 232-Th | 14.0 max | 0.08 ± 0.03 | Reported by: K.H.Sun et al., Phys.Rev., vol. 79, 3, 1950. | ||
6 | 232-Th | 3 | 0.0476 ± 0.0080 | 0.0568 ± 0.0145 | Reported by: Brunson G.S. et al. Nucl. Sci. Eng., 1956, v.1, p.174. Adjusted by: R.J. Tuttle, 1979. | |
7 | 232-Th | 3 | 0.038 ± 0.008 | 0.0375 ± 0.0090 | Reported by: H. Rose and R. D. Smith, J. Nucl. Energy, vol.1, 4, 133 (1957). Adjusted by: R.J. Tuttle, 1979. | |
8 | 232-Th | 3 | 0.038 ± 0.008 | 0.0369 ± 0.0045 | Reported by: H. Rose and R. D. Smith, J. Nucl. Energy, vol.1, 4, 133 (1957). Adjusted by: Cox, 1974 | |
9 | 232-Th | 3.5 FSCSW | 0.0496 ± 0.0020 | 0.0505 ± 0.0052 | Reported by: Keepin G.R., Wimett T.F., Zeigler R.K., J. Nucl. Energy, 6, 1, (1957), and Phys. Rev., 107, 1044 (1957). Adjusted by: R.J. Tuttle, 1979. | |
10 | 232-Th | 3.5 FSCSW | 0.0496 ± 0.0020 | 0.0496 ± 0.0035 | Reported by: Keepin G.R., Wimett T.F., Zeigler R.K., J. Nucl. Energy, 6, 1, (1957), and Phys. Rev., 107, 1044 (1957). Adjusted by: Zamyatnin, 1976. | |
11 | 232-Th | 3.5 FSCSW | 0.0496 ± 0.0020 | 0.0505 ± 0.0020 | Reported By: Keepin G.R., Wimett T.F., Zeigler R.K., J. Nucl. Energy, 6, 1, (1957), and Phys. Rev., 107, 1044 (1957). Adjusted by: Cox, 1974. | |
12 | 232-Th | 2.4 | 0.0524 ± 0.0040 | 0.0571 ± 0.0051 | Reported by: B.P.Maksyutenko, Soviet At.Energ.,vol.7,943 (1961), translated from Atom.Energ. Vol.7,474 (1959). Adjusted by: R.J. Tuttle,1979. | |
13 | 232-Th | 3.3 | 0.049 ± 0.004 | 0.0534 ± 0.0048 | Reported by: B.P.Maksyutenko, Soviet At.Energ.,vol.7,943 (1961) translated from Atom.Energ. Vol.7,474 (1959). Adjusted by: R.J. Tuttle,1979. | |
14 | 232-Th | 15.0 | 0.079 ± 0.006 | 0.0835 ± 0.0069 | ||
15 | 232-Th | 14.0 | 0.058 ± 0.014 | Reported by: W.E.McGarry et al., Bull.Am.Phys.Soc.II,vol.5,33 (1960). | ||
16 | 232-Th | 14.5 | 0.075 ± 0.007 | 0.0782 ± 0.0075 | "Reported by V. I. Shpakov , K. A. Petrzhak , M. A. Bak , S. S. Kovolenko , an d . I. Kostochkin , Atomnaya Energiya 11 , 53 9 (1961) . | |
17 | 232-Th | 14.0 | 0.019 ± 0.005 | 0.0218 ± 0.0030 | Reported by: G. Herrmann, Delayed Fission Neutrons, Proc. Panel, International Atomic Energy Agency, Vienna (1968). Adjusted by: R.J. Tuttle, 1979. | |
18 | 232-Th | 14.0 | 0.019 ± 0.005 | 0.0205 ± 0.0027 | Reported by: G. Herrmann, Delayed Fission Neutrons, Proc. Panel, International Atomic Energy Agency, Vienna (1968). Adjusted by: Cox 1974. | |
19 | 232-Th | 14.8 | 0.019 ± 0.005 | 0.019 ± 0.003 | Reported by: G. Herrmann, Delayed Fission Neutrons, Proc. Panel, International Atomic Energy Agency, Vienna (1968). Adjusted by: Zamyatnin 1976. | |
20 | 232-Th | 3.1 | 0.060 ± 0.006 | 0.0566 ± 0.0042 | Reported by: C. F. Masters, et al., Nucl. Sci. Eng. 36, 202, 1969. Adjusted by: Evans A.E. et al., Nucl. Sci. Eng., 1973, v. 50, p. 80. | |
21 | 232-Th | 14.9 | 0.030 ± 0.002 | 0.030 ± 0.002 | Reported by: C. F. Masters, et al., Nucl. Sci. Eng. 36, 202, 1969. Adjusted by: Evans A.E. et al., Nucl. Sci. Eng., 1973, v. 50, p. 80. | |
22 | 232-Th | 3.1 | 0.060 ± 0.006 | 0.0570 ± 0.0050 | Reported by: C. F. Masters, et al., Nucl. Sci. Eng. 36, 202, 1969. Adjusted by: Zamyatnin, 1976. | |
23 | 232-Th | 3.1 | 0.060 ± 0.006 | 0.0570 ± 0.0040 | Reported by: C. F. Masters, M.M. Thrope, and D.B. Smith, Nucl. Sci. Eng., 36, 202, (1969). Adjusted by: Cox, 1974. | |
24 | 232-Th | 14.1 | 0.0119±0.0014 | 0.0311 ± 0.0037 | Reported by: Keepin G.R.et al. Rep. LA-4227-MS, 1969, p. 17; LA-4320-MC, 1969. Adjusted by: R.J. Tuttle, 1979. | |
25 | 232-Th | 14.1 | 0.0119±0.0014 | 0.0315 ± 0.0037 | Reported by: G.R. Keepin (editor), LA-4227-MS, Los Alamos Scientific Laboratory (1969). Adjusted by: Cox, 1974. | |
26 | 232-Th | 14.9 | 0.0123±0.0011 | 0.0287 ± 0.0026 | Reported by: Keepin G.R.et al. Rep. LA-4227-MS, 1969, p. 17; LA-4320-MC, 1969. Adjusted by: R.J. Tuttle, 1979. | |
27 | 232-Th | 14.9 | 0.0123±0.0011 | 0.0300 ± 0.0030 | Reported by: Keepin G.R.et al. Rep. LA-4227-MS, 1969, p. 17; LA-4320-MC, 1969. Adjusted by: Zamyatnin, 1976. | |
28 | 232-Th | 14.9 | 0.0123±0.0011 | 0.0287 ± 0.0026 | Reported by: Keepin G.R.et al. Rep. LA-4227-MS, 1969, p. 17; LA-4320-MC, 1969. Adjusted by: Cox, 1974. | |
29 | 232-Th | 14 | 0.0170 ± 0.0072 | Reported by: Notea A. , Rep. IA-1190, P.95, Israel Atomic Energy Comm. (1969). Adjusted by: R.J. Tuttle, 1979. | ||
30 | 232-Th | 14 | 0.0128 ± 0.0050 | Reported by: A. Notea, Rep. IA-1190, P.95, Israel Atomic Energy Comm. (1969). Adjusted by: Cox, 1974. | ||
31 | 232-Th | 14.8 | 0.014 ± 0.005 | Reported by: A. Notea, Rep. IA-1190, P.95, Israel Atomic Energy Comm. (1969). Adjusted by: Manero F. , Atomic Energy Rev.,1972, v.10, No.4, p.657. | ||
32 | 232-Th | 14 | 0.0191 ± 0.0065 | 0.0209 ± 0.0042 | Reported by: G.Benedict, Annual report 1968, BMBW-FB K70-04, University of Mainz (1970). Adjusted by: R.J. Tuttle, 1979. | |
33 | 232-Th | 14.8 | 0.019 ± 0.006 | Reported by: Benedict G. et al., Radiochem. Acta, 1972, Bd 17, +-1, S.61. Adjusted by: Zamyatnin, 1976. | ||
34 | 232-Th | 1.3 - 1.6 | 0.0505 | 0.0525 + 0.0040 | Reported by: Cox S.A., Whiting D.E.E. Rep. ANL-7610, 1970, p.45. Adjusted by: R.J. Tuttle, 1979. | |
35 | 232-Th | 1.3 | 0.0465 ± 0.0030 | Reported by: Cox S.A., Whiting D.E.E. Rep. ANL-7610, 1970, p.45. | ||
36 | 232-Th | 1.35 | 0.0490 ± 0.0025 | |||
37 | 232-Th | 1.4 | 0.0540 ± 0.0020 | |||
38 | 232-Th | 1.5 | 0.0505 ± 0.0020 | |||
39 | 232-Th | 1.6 | 0.0530 ± 0.0025 | |||
40 | 232-Th | 14.8 | 0.0269 ± 0.0040 | 0.0286 ± 0.0048 | Reported by: Brown M.G. et al., Radiochem. Acta, 1971, Bd 15, S. 109. Adjusted by: R.J. Tuttle, 1979. | |
41 | 232-Th | 14.8 | 0.0269 ± 0.0040 | 0.036 ± 0.007 | Reported by: Brown M.G. et al., Radiochem. Acta, 1971, Bd 15, S. 109. Adjusted by Zamyatnin, 1976. | |
42 | 232-Th | 14.9 | 0.030 ± 0.0030 | Evans A.E. et al. Nucl. Sci. Eng., 1973, v. 50, p. 80. | ||
43 | 232-Th | 14.9 | 0.0300 ± 0.0027 | C. F. Masters, M.M. Thrope, and D.B. Smith, Nucl. Sci. Eng., 36, 202, (1969). | ||
44 | 232-Th | fast | 0.0527 ± 0.0040 | R.W. Waldo, R.A. Karam, R.A. Meyer. Delayed neutron yields: Time dependent measurements and a predictive model. Phys. Rev., C, V. 23, No. 3, 1981. | ||
45 | 232-Th | 3.2 | 0.0579 ± 0.0023 | V.M. Piksaikin, A.S. Egorov, K.V. Mitrofanov, A.A. Goverdovski. Total delayed neutron yields for neutron induced fission of 232Th in energy range 3.2-4.9 MeV. Atomic Energy, V. 112, No. 6, pp.350-355, 2012.; Piksaikin V.M., Egorov A.S., Mitrofanov K.V. The absolute total delayed neutron yields, relative abundances and half-life of delayed neutron groups from neutron induced fission of 232Th, 233U, 236U, 239Pu AND 241Am. Report INDC(NDS) - 0646, 2013, IAEA, Vienna, Austria. | ||
46 | 232-Th | 3.8 | 0.0572 ± 0.0024 | |||
47 | 232-Th | 4.2 | 0.0550 ± 0.0042 | |||
48 | 232-Th | 4.5 | 0.0557 ± 0.0063 | |||
49 | 232-Th | 4.7 | 0.0543 ± 0.0031 | |||
50 | 232-Th | 4.9 | 0.0568 ± 0.0032 | |||
51 | 232-Th | 1.996 | 0,0592 ± 0,0035 | X. Ledoux et al., Delayed neutron measurements of 232Th neutron-induced fission. Annals of Nuclear Energy 76 (2015) 514�520 | ||
52 | 232-Th | 2.974 | 0,0565 ± 0,0035 | X. Ledoux et al., Delayed neutron measurements of 232Th neutron-induced fission. Annals of Nuclear Energy 76 (2015) 514�521 | ||
53 | 232-Th | 3.999 | 0,0549 ± 0,0034 | X. Ledoux et al., Delayed neutron measurements of 232Th neutron-induced fission. Annals of Nuclear Energy 76 (2015) 514�522 | ||
54 | 232-Th | 3.999 | 0,0564 ± 0,0035 | X. Ledoux et al., Delayed neutron measurements of 232Th neutron-induced fission. Annals of Nuclear Energy 76 (2015) 514�523 | ||
55 | 232-Th | 5.997 | 0,0359 ± 0,0023 | X. Ledoux et al., Delayed neutron measurements of 232Th neutron-induced fission. Annals of Nuclear Energy 76 (2015) 514�524 | ||
56 | 232-Th | 6.967 | 0,0310 ± 0,0018 | X. Ledoux et al., Delayed neutron measurements of 232Th neutron-induced fission. Annals of Nuclear Energy 76 (2015) 514�525 | ||
57 | 232-Th | 10.024 | 0,0292 ± 0,0025 | X. Ledoux et al., Delayed neutron measurements of 232Th neutron-induced fission. Annals of Nuclear Energy 76 (2015) 514�526 | ||
58 | 232-Th | 15.936 | 0,0258 ± 0,0017 | X. Ledoux et al., Delayed neutron measurements of 232Th neutron-induced fission. Annals of Nuclear Energy 76 (2015) 514�527 | ||
59 | 232-Th * | less than 4.0 | 0.0527 ± 0.0040 | Reported by: Cox, 1974. | ||
60 | 232-Th * | 4.0-7.0 | 0.0414 ± 0.0040 | |||
61 | 232-Th * | 7.0-20.0 | 0.030 ± 0.004 | |||
62 | 232-Th * | fast | 0.0531 ± 0.0023 | Reported by: R.J. Tuttle. Delayed-neutron yields in nuclear fission. Procedings of the consultants' meeting on delayed neutron properties, Vienna, 26-30 March 1979. INDC(NDS)-107/G+Special. pp. 29-67, 1979. | ||
232-Th | Photofission | |||||
63 | 232-Th | 12. 20 | 0.0285 ± 0.008 | Reported by: G. Moscati and J. Goldemberg, Phys. Rev., 126, 1098 (1962). | ||
64 | 232-Th | 12 | 0.0285 ± 0.008 | 0.027 ± 0.008 | Reported by: G. Moscati and J. Goldemberg, Phys. Rev., 1962, v. 126, p. 1098. Adjusted by: Zamyatnin,1976. | |
65 | 232-Th | 20 | 0.0285 ± 0.008 | 0.030 ± 0.012 | ||
66 | 232-Th | 15 | 0.038 ± 0.006 | Reported by: O.P. Nikotin and K.A. Petrzhak, Soviet At. Energy, 20, No.3, 268 (1966). | ||
67 | 232-Th | 8-12 | 0.0280 ± 0.0012 | Reported by: J. T. Caldwell, E. J. Dowdy, and G. M. Worth, Physics and Chemistry of Fission 1973, Vol. I, p 431, IAEA, Vienna (1974). | ||
68 | 232-Th | 8-13 | 0.0280 ± 0.0028 | Reported by: J. T. Caldwell and E. J. Dowdy, Nucl. Sci. Eng., 56, 179 (1975). Adjusted by: Zamyatnin,1976. | ||
69 | 232-Th | 6.44 | 0.0310 ± 0.0028 | |||
70 | 232-Th | 7.02 | 0.0306 ± 0.0031 | |||
71 | 232-Th | 7.10 | 0.0267 ± 0.0021 | |||
72 | 232-Th | 8.06 | 0.0259 ± 0.0031 | |||
232-Th | Charged Particle Fission | |||||
73 | 232-Th | 21.7 (He-3) | 0.022 ± 0.004 | Reported by: E. T. Chulick and P. l. Reeder, Nucl. Phys, A173, 497 (1971). | ||
74 | 232-Th | 23.3 (He-3) | 0.021 ± 0.003 | |||
75 | 232-Th | 28.9 (He-3) | 0.013 ± 0.002 | |||
76 | 232-Th | 33.8 (He-3) | 0.0044 ± 0.0009 | |||
77 | 232-Th | 19.9 (He-4) | 0.053 ± 0.010 | |||
78 | 232-Th | 28.9 (He-4) | 0.018 ± 0.002 | |||
232-U | Neutron induced fission | |||||
79 | 232-U | fast | 0.0044 ± 0.0003 | Reported by: R.W. Waldo, R.A. Karam, R.A. Meyer, Phys. Rev., C, V. 23, No. 3, 1981. | ||
233-U | Neutron induced fission | |||||
80 | 233-U | Thermal | 0.0060 ± 0.0005 | 0.00629 ± 0.00073 | Reported by: Brunson G.S. et al. Nucl. Sci. Engng., 1956, v.1, p.174. Adjusted by: R.J. Tuttle, 1979. | |
81 | 233-U | 0.27 | 0.0064 ± 0.0005 | 0.00652 + 0.00075 | ||
82 | 233-U | thermal | 0.0060 ± 0.0005 | 0.0065 ± 0.0005 | Reported by: Brunson G.S. et al. Nucl. Sci. Eng., 1956, v.1, p.174. Adjusted by: Zamyatnin, 1976. | |
83 | 233-U | 1 | 0.0074 ± 0.0006 | 0.00737 ± 0.00080 | Reported by: H. Rose and R. D. Smith, J. Nucl. Energy, vol.1, 4, 133 (1957). Adjusted by: R.J. Tuttle, 1979. | |
84 | 233-U | 1 | 0.0074 ± 0.0006 | 0.00716±0.00043 | Reported by: H. Rose and R. D. Smith, J. Nucl. Energy, vol.1, 4, 133 (1957). Adjusted by: Cox, 1974. | |
85 | 233-U | Thermal | 0.0066 ± 0.0003 | 0.0066 ± 0.0007 | Reported by: Keepin G.R., et al., Phys. Rev., 1957, v 107,p 1044 and also G.R.Keepin,et al.,J. Nucl. Energy, 6,1(1957). Adjusted by: R.J. Tuttle, 1979. | |
86 | 233-U | 1.45 FSCSW | 0.0070 ± 0.0004 | 0.00729 ± 0.00081 | ||
87 | 233-U | thermal | 0.0066 ± 0.0003 | 0.0066 ± 0.0005 | Reported by: Keepin G.R., Wimett T.F., Zeigler R.K. Phys. Rev., 1957, v 107, p 1044. Adjusted by: Zamyatnin, 1976. | |
88 | 233-U | 1.45 FSCSW | 0.0070 ± 0.0004 | 0.0070 ± 0.0006 | ||
89 | 233-U | thermal | 0.0066 ± 0.0003 | 0.0066 ± 0.0003 | Reported by: Keepin G.R., Wimett T.F., Zeigler R.K., J. Nucl. Energy, 6, 1, (1957), and Phys. Rev., 107, 1044 (1957). Adjusted by: Cox, 1974. | |
90 | 233-U | 1.45 FSCSW | 0.0070 ± 0.0004 | 0.0073 ± 0.0004 | ||
91 | 233-U | 14 | 0.0142 ± 0.0042 | Reported by: W.E.McGarry et al., Bull.Am.Phys.Soc.II,vol.5,33 (1960). | ||
92 | 233-U | 3.1 | 0.0077 ± 0.0008 | 0.00751 ± 0.00061 | Reported by: Masters C.F. et al. Nucl. Sci. Eng., 1969, v. 36, p.202. Adjusted by: R.J. Tuttle, 1979. | |
93 | 233-U | 3.1 | 0.0077 ± 0.0008 | 0.0074 ± 0.0006 | Reported by: Masters C.F. et al. Nucl. Sci. Eng., 1969, v. 36, p.202. Adjusted by: Zamyatnin, 1976. | |
94 | 233-U | 3.1 | 0.0077 ± 0.0008 | 0.0074 ± 0.0008 | Reported by: C. F. Masters, M.M. Thrope, and D.B. Smith, Nucl. Sci. Eng., 36, 202, (1969). Adjusted by: Cox, 1974. | |
95 | 233-U | 14.9 | 0.0041 ± 0.0003 | 0.0043 ± 0.0004 | Reported by: C. F. Masters, M.M. Thrope, and D.B. Smith, Nucl. Sci. Eng., 36, 202, (1969). Adjusted by: Evans A.E. et al. Nucl. Sci. Eng., 1973, v. 50, p. 80. | |
96 | 233-U | 14.1 | 0.0109 ± 0.0010 | 0.00439 ± 0.00041 | Reported by: Keepin G.R.et al. Rep. LA-4227-MS, 1969, p. 17; LA-4320-MC, 1969. Adjusted by: R.J.Tuttle, 1979. | |
97 | 233-U | 14.9 | 0.0109 ± 0.0011 | 0.00433 ± 0.00044 | ||
98 | 233-U | 14.9 | 0.0109 ± 0.0011 | 0.0046 ± 0.0005 | Reported by: Keepin G.R.et al. Rep. LA-4227-MS, 1969, p. 17; LA-4320-MC, 1969. Adjusted by: Zamyatnin 1976 | |
99 | 233-U | 14.1 | 0.0109 ± 0.0010 | 0.00439 ± 0.00044 | Reported by: G.R. Keepin (editor), LA-4227-MS, Los Alamos Scientific Laboratory (1969). Adjusted by: Cox, 1974. | |
100 | 233-U | 14.9 | 0.0109 ± 0.0011 | 0.00433 ± 0.00044 | ||
101 | 233-U | Thermal | 0.0082 ± 0.0026 | Reported by: Notea A., Israel Atomic Energy Comm. Rep. IA-1190, 1969, p.95. Adjusted by: R.J. Tuttle, 1979. | ||
102 | 233-U | Thermal | 0.0054 ± 0.0013 | Reported by: Notea A., Israel Atomic Energy Comm. Rep. IA-1190, 1969, p.95. Adjusted by: Zamyatnin, 1976. | ||
103 | 233-U | Thermal | 0.00575 ± 0.00140 | Reported by: A. Notea, Report IA-1190, P.95, Israel Atomic Energy Comm. (1969). Adjusted by: Cox, 1974. | ||
104 | 233-U | Thermal | β = 0.0027 ± 0.0001 | 0.00674 ± 0.00042 | Reported by: Conant J.F., Palmedo P.F. Nucl. Sci. Eng., 1971, v.44, p. 173. (R.J. Tuttle, 1979)Adjusted by: R.J. Tuttle, 1979 | |
105 | 233-U | Thermal | β = 0.0027 ± 0.0001 | 0.0067 ± 0.0003 | Reported by: Conant J.F., Palmedo P.F. Nucl. Sci. Eng., 1971, v.44, p. 173. Adjusted by: Zamyatnin, 1976. | |
106 | 233-U | Thermal | β = 0.0027 ± 0.0001 | 0.00671 ± 0.00041 | Reported by: J. F. Conant and P.F. Palmeda, Nucl. Sci. Eng., 44, 173 (1971). Adjusted by: Cox, 1974. | |
107 | 233-U | 0.1 - 1.8 | 0.0075 ± 0.0006 | Reported by: Krick M.S. et al., Nucl.Sci.Eng.1972,v.47,p.311, Trans.Amer.Nucl.Soc.,1970, v.13,p.746. Adjusted by: Evans A.E. et al. Nucl. Sci. Eng., 1973, v. 50, p. 80. | ||
108 | 233-U | 14.9 | 0.0041 ± 0.0003 | 0.0041 ± 0.0003 | ||
109 | 233-U | 0.05 | 0.00735 ± 0.00064 | Reported by: Krick M.S. et al., Nucl.Sci.Eng.1972,v.47,p.311. Adjusted by: Evans A.E. et al. Nucl. Sci. Eng., 1973, v. 50, p. 80. | ||
110 | 233-U | 0.11 | 0.00735 ± 0.00064 | |||
111 | 233-U | 0.21 | 0.00730 ± 0.00064 | |||
112 | 233-U | 0.32 | 0.00741 ± 0.00064 | |||
113 | 233-U | 0.43 | 0.00734 ± 0.00064 | |||
114 | 233-U | 0.53 | 0.00745 ± 0.00065 | |||
115 | 233-U | 0.64 | 0.00745 ± 0.00065 | |||
116 | 233-U | 0.74 | 0.00759 ± 0.00066 | |||
117 | 233-U | 0.84 | 0.00759 ± 0.00066 | |||
118 | 233-U | 0.94 | 0.00749 ± 0.00065 | |||
119 | 233-U | 1.05 | 0.00759 ± 0.00066 | |||
120 | 233-U | 1.15 | 0.00759 ± 0.00066 | |||
121 | 233-U | 1.25 | 0.00744 ± 0.00065 | |||
122 | 233-U | 1.35 | 0.00765 ± 0.00066 | |||
123 | 233-U | 1.45 | 0.00765 ± 0.00066 | |||
124 | 233-U | 1.55 | 0.00759 ± 0.00066 | |||
125 | 233-U | 1.65 | 0.00739 ± 0.00064 | |||
126 | 233-U | 1.75 | 0.00759 ± 0.00066 | |||
127 | 233-U | 4 | 0.0080 ± 0.0009 | |||
128 | 233-U | 4.5 | 0.0074 ± 0.0009 | |||
129 | 233-U | 5.1 | 0.0070 ± 0.0008 | |||
130 | 233-U | 5.35 | 0.0065 ± 0.0008 | |||
131 | 233-U | 5.6 | 0.0055 ± 0.0007 | |||
132 | 233-U | 6.1 | 0.0050 ± 0.0006 | |||
133 | 233-U | 6.6 | 0.0051 ± 0.0006 | |||
134 | 233-U | Thermal | 0.0074 ± 0.0004 | Reported by: R.W. Waldo, R.A. Karam, R.A. Meyer. Phys. Rev., C, V. 23, No. 3, 1981. | ||
135 | 233-U | 0.34 ± 0.07 | 0.00746 ± 0.00037 | Reported by: Piksaikin V.M., Egorov A.S., Mitrofanov K.V. , Report INDC(NDS) - 0646, 2013, IAEA, Vienna, Austria; | ||
136 | 233-U | 0.59 ± 0.08 | 0.00748 ± 0.00037 | V.M. Piksaikin et al., Instruments and Experimental Techniques, 49(6), pp.765-777, January 2006. (DOI: | ||
137 | 233-U | 0.81 ± 0.09 | 0.00746 ± 0.00035 | 10.1134/S0020441206060030). | ||
138 | 233-U | 1.01 ± 0.10 | 0.00744 ± 0.00037 | |||
139 | 233-U | 3.23 ± 0.15 | 0.00794 ± 0.00039 | |||
140 | 233-U | 3.75 ± 0.14 | 0.00804 ± 0.00040 | |||
141 | 233-U | 4.20 ± 0.17 | 0.00760 ± 0.00038 | |||
142 | 233-U | 4.72 ± 0.21 | 0.0069 ± 0.0003 | |||
143 | 233-U | 4.90 ± 0.21 | 0.00668 ± 0.00033 | |||
144 | 233-U | Thermal | 0.00674 ± 0.00022 | Reported by: S.B. Borzakov et al., Physics of Atomic Nuclei, Vol. 63, No. 4, 2000, pp. 589-597. | ||
145 | 233-U * | less than 4.5 | 0.0074 ± 0.0004 | Reporeted by: Cox 1974. | ||
146 | 233-U * | 4.5-7.0 | 0.0059 ± 0.0004 | |||
147 | 233-U * | 7.0-20.0 | 0.0044 ± 0.0005 | |||
148 | 233-U * | thermal | 0.00667 ± 0.00029 | Reported by: R.J. Tuttle, Report INDC(NDS)-107/G+Special. pp. 29-67, 1979, IAEA, Vienna, Austria. | ||
149 | 233-U * | fast | 0.00731 ± 0.00036 | |||
233-U | Photofission | |||||
150 | 233-U | 8-13 | 0.00553 ± 0.00044 | Reported by: J. T. Caldwell and E. J. Dowdy, Nucl. Sci. Eng., 56, 179 (1975). | ||
151 | 233-U | 6.68 | 0.00455 ± 0.00045 | Reported by: Caldwell J. T., Dowdy E. J. - Nucl. Sci. Eng., 1975, v. 56, 179. Adjusted by: Zamyatnin, 1976. | ||
152 | 233-U | 7.9 | 0.00518 ± 0.00040 | |||
153 | 233-U | 9.55 | 0.00640 ± 0.00044 | |||
154 | 233-U | 10.27 | 0.00598 ± 0.00051 | |||
234-U | Photofission | |||||
155 | 234-U | 8-13 | 0.0094 ± 0.00094 | Reported by: J. T. Caldwell and E. J. Dowdy, Nucl. Sci. Eng., 56, 179 (1975). | ||
156 | 234-U | 8.69 | 0.0092 ± 0.0006 | Reported by: Caldwell J. T., Dowdy E. J. - Nucl. Sci. Eng., 1975, v. 56, 179. Adjusted by: Zamyatnin, 1976. | ||
157 | 234-U | 9.54 | 0.0097 ± 0.0012 | |||
235-U | Neutron induced fission | |||||
158 | 235-U | Thermal | β = 0.010 ± 0.002 | 0.0176 ± 0.0054 | Reported by: A.H.Snell et al., Phys.Rev.,vol.72, 541 (1947). Adjusted by: R.J.Tuttle,1979. | |
159 | 235-U | Thermal | β = 0.00755 ± 0.00050 | 0.0183 ± 0.0026 | Reported by: D.J.Hughes et al., Phys.Rev., vol.73,111 (1948). Adjusted by: R.J.Tuttle,1979. | |
160 | 235-U | thermal | β = 0.00755 ± 0.00050 | 0.0183 ± 0.0014 | Reported by: D.J.Hughes et al., Phys.Rev., vol.73,111 (1948). Adjusted by: Zamyatnin, 1976. | |
161 | 235-U | Thermal | 0.0175 ± 0.0028 | Brunson G.S. et al. Nucl. Sci. Eng., 1956, v.1, p.174. Adjusted by: R.J.Tuttle,1979. | ||
162 | 235-U | 0.29 | 0.0172 ± 0.0023 | |||
163 | 235-U | thermal | 0.0168 ± 0.0018 | Brunson G.S. et al. Nucl. Sci. Eng., 1956, v.1, p.174. Adjusted by: Zamyatnin 1976. | ||
164 | 235-U | 1 | 0.0174 ± 0.0014 | 0.0174 ± 0.0019 | "Reported by: H. Rose and R. D. Smith, ""J. Nucl. Energy"", vol.1, 133 (1957). Adjusted by: R.J. Tuttle, 1979." | |
165 | 235-U | Thermal | 0.0158 ± 0.0005 | 0.0158 ± 0.0016 | Reported by: G. R. Keepin, T. F. Wimett, and R. K. Zeigler, J. Nucl. Energy, 6, 1 (1957). Adjusted by: R.J.Tuttle,1979. | |
166 | 235-U | 1.45 FSCSW | 0.0165 ± 0.0005 | 0.01675 ± 0.0017 | ||
167 | 235-U | thermal | 0.0158 ± 0.0005 | 0.0158 ± 0.0007 | Reported by: Keepin G. R., Wimett T. F., and Zeigler R. K. - Phys. Rev., 1957, v. 107, p. 1044. Adjusted by: Zamyatnin 1976. | |
168 | 235-U | 1.45 FSCSW | 0.0165 ± 0.0005 | 0.0165 ± 0.0007 | ||
169 | 235-U | thermal | 0.0158 ± 0.0005 | 0.0158 ± 0.0007 | Reported by: Keepin G.R., Wimett T.F., Zeigler R.K., J. Nucl. Energy, 6, 1, (1957), and Phys. Rev., 107, 1044 (1957). Adjusted by: Cox, 1974. | |
170 | 235-U | 1.45 FSCSW | 0.0165 ± 0.0005 | 0.0167 ± 0.0007 | ||
171 | 235-U | Thermal | (reference data) | 0.0173 ± 0.0012 | Reported by: B.P.Maksyutenko, Soviet At.Energ.,vol.7,943 (1961) translated from Atom.Energ. Vol.7,474 (1959). Adjusted by: R.J.Tuttle,1979. | |
172 | 235-U | 2.4 | 0.0178 ± 0.0012 | |||
173 | 235-U | 3.3 | 0.0171 ± 0.0012 | |||
174 | 235-U | 15 | 0.0304 ± 0.0015 | |||
175 | 235-U | 14 | 0.022 ± 0.005 | Reported by: W.E.McGarry et al., Bull.Am.Phys.Soc.II,vol.5,33 (1960). | ||
176 | 235-U | Thermal | 0.0221 ± 0.0031 | Reported by: G. Herrmann, Delayed Fission Neutrons, Proc. Panel, International Atomic Energy Agency, Vienna (1968). | ||
177 | 235-U | 3.1 | 0.0173 ± 0.0012 | Reported by: C. F. Masters, M. M. Thorpe, and D. B. Smith, Nucl. Sci. Eng., 36,202 (1969). Adjusted by: R.J.Tuttle,1979. | ||
178 | 235-U | 14.9 | 0.0095 ± 0.0008 | Reported by: Evans A.E. et al. Nucl. Sci. Eng., 1973, v. 50, p. 80. | ||
179 | 235-U | 3.1 | 0.0172 ± 0.0013 | Reported by: C. F. Masters, M.M. Thrope, and D.B. Smith, Nucl. Sci. Eng., 36, 202, (1969). Adjusted by: Cox, 1974. | ||
180 | 235-U | 14.1 | 0.0212 ± 0.0017 | 0.0094 ± 0.0008 | Reported by: G.R.Keepin, Rep. LA-4227-MS, Los Alamos scientific laboratory, 1969, p. 17; LA-4320-MC, 1969. Adjusted by: R.J.Tuttle,1979. | |
181 | 235-U | 14.9 | 0.0214 ±0.0017 | 0.0092 ± 0.0007 | ||
182 | 235-U | 14.9 | 0.0214 ±0.0017 | 0.0098 ± 0.0008 | Reported by: G.R. Keepin, Rep. LA-4227-MS, 1969, p. 17; LA-4320-MC, 1969. Adjusted by: Zamyatnin 1976. | |
183 | 235-U | 14.1 | 0.0212 ± 0.0017 | 0.0089 ± 0.0007 | Reported by: G.R. Keepin (editor), LA-4227-MS, Los Alamos Scientific Laboratory (1969). Adjusted by: Cox, 1974. | |
184 | 235-U | 14.9 | 0.0214 ±0.0017 | 0.0088 ± 0.0007 | ||
185 | 235-U | Thermal | 0.0254 ± 0.0081 | Reported by: Notea A., Israel Atomic Energy Comm., Rep. IA-1190, 1969, p.95. Adjusted by: R.J.Tuttle,1979. | ||
186 | 235-U | thermal | 0.0205 ± 0.0061 | Reported by: Notea A., Israel Atomic Energy Comm., Rep. IA-1190, 1969, p.95. Adjusted by: Zamyatnin 1976 | ||
187 | 235-U | Thermal | 0.0217 ± 0.0039 | Reported by: G.Benedict, Annual report 1968, BMBW-FB K70-04, University of Mainz (1970). Adjusted by: R.J. Tuttle, 1979. | ||
188 | 235-U | 0.25 - 1.5 | 0.0170 ± 0.0011 | Reported by: Cox S.A., Whiting D.E.E. Rep. ANL-7610, 1970, p.45. Adjusted by: R.J. Tuttle, 1979. | ||
189 | 235-U | 0.25 | 0.0171 ± 0.0008 | Reported by: Cox S.A., Whiting D.E.E. Rep. ANL-7610, 1970, p.45. | ||
190 | 235-U | 0.6 | 0.0170 ± 0.0008 | |||
191 | 235-U | 1 | 0.0167 ± 0.0008 | |||
192 | 235-U | 1.2 | 0.0167 ± 0.0008 | |||
193 | 235-U | 1.5 | 0.0165 ± 0.0007 | |||
194 | 235-U | Thermal | β = 0.0065 ± 0.0003 | 0.0157 ± 0.0010 | Reported by: Conant J.F., Palmedo P.F. Nucl. Sci. Eng., 1971, v.44, p. 173. Adjusted by: R.J. Tuttle, 1979. | |
195 | 235-U | thermal | β = 0.0065 ± 0.0003 | 0.0158 ± 0.0007 | Reported by: Conant J.F., Palmedo P.F. Nucl. Sci. Eng., 1971, v.44, p. 173. Adjusted by: Zamyatnin, 1976. | |
196 | 235-U | thermal | β = 0.0065 ± 0.0003 | 0.0158 ± 0.0010 | Reported by: Conant J.F., Palmeda P.F. Nucl. Sci. Eng., 1971, v.44, p. 173.Adjusted by: Cox, 1974. | |
197 | 235-U | 0.1 - 1.8 (averaged) | 0.0163 ± 0.0013 | Reported by:Krick M.S. et al., Nucl.Sci. Eng.,1972,v.47,p.311, Trans.Amer.Nucl.Soc.,1970,v.13,p.746. | ||
198 | 235-U | 0.5 | 0.0165 ± 0.0013 | Reported by: Krick M.S. et al., Nucl.Sci.Eng.1972,v.47,p.311, Trans.Amer.Nucl.Soc.,1970,v.13,p.746. Adjusted by: Evans A.E. et al. Nucl. Sci. Eng., 1973, v. 50, p. 80. | ||
199 | 235-U | 0.15 | 0.0162 ± 0.0012 | |||
200 | 235-U | 0.25 | 0.0166 ± 0.0013 | |||
201 | 235-U | 0.36 | 0.0165 ± 0.0013 | |||
202 | 235-U | 0.46 | 0.0162 ± 0.0012 | |||
203 | 235-U | 0.56 | 0.0160 ± 0.0012 | |||
204 | 235-U | 0.67 | 0.0160 ± 0.0012 | |||
205 | 235-U | 0.77 | 0.0162 ± 0.0012 | |||
206 | 235-U | 0.87 | 0.0163 ± 0.0013 | |||
207 | 235-U | 0.97 | 0.0160 ± 0.0012 | |||
208 | 235-U | 1.07 | 0.0163 ± 0.0013 | |||
209 | 235-U | 1.17 | 0.0167 ± 0.0013 | |||
210 | 235-U | 1.27 | 0.0171 ± 0.0013 | |||
211 | 235-U | 1.37 | 0.0170 ± 0.0013 | |||
212 | 235-U | 1.47 | 0.0160 ± 0.0012 | |||
213 | 235-U | 1.56 | 0.0167 ± 0.0013 | |||
214 | 235-U | 1.65 | 0.0163 ± 0.0013 | |||
215 | 235-U | 1.75 | 0.0161 ± 0.0012 | |||
216 | 235-U | 4 | 0.0153 ± 0.0015 | |||
217 | 235-U | 4.4 | 0.0146 ± 0.0015 | |||
218 | 235-U | 4.8 | 0.0151 ± 0.0014 | |||
219 | 235-U | 5.1 | 0.0136 ± 0.0014 | |||
220 | 235-U | 5.6 | 0.0125 ± 0.0013 | |||
221 | 235-U | 5.7 | 0.0111 ± 0.0013 | |||
222 | 235-U | 6 | 0.0123 ± 0.0013 | |||
223 | 235-U | 6.4 | 0.0102 ± 0.0012 | |||
224 | 235-U | 6.7 | 0.0105 ± 0.0012 | |||
225 | 235-U | 0.63 | 0.0174 ± 0.0015 | "Reported by: Clifford D.A., McTaggart H.N. (data are presented in Tomlinson L. Delayed neutrons from fission, Rep. AERE-R 6993, ""A compilation and evaluation of experimental data"", 1972.)" | ||
226 | 235-U | 0.63 | 0.0174 ± 0.0015 | 0.0174 ± 0.0008 | Reported by: D.A. Clifford et al. Adjusted by: Cox,1974, on the basis of paper reported by M.H. McTaggart in Fast Integral Assembly Newsletter Nos. 19-22, March 1972. | |
227 | 235-U | 0.96 | 0.01650 ± 0.00100 | "Reported by: Cox S. A. , ""Delayed Neutron Data - Review and Evaluation,"" ANL/NDM-5, Argonne National Laboratory (1974)." | ||
228 | 235-U | 1.97 | 0.01657 ± 0.00100 | |||
229 | 235-U | 2.98 | 0.01696 ± 0.00100 | |||
230 | 235-U | 3.98 | 0.01666 ± 0.00100 | |||
231 | 235-U | 0.63 | 0.0164 ± 0.0006 | 0.0166 ± 0.0006 | "Reported by: C. B. Besant, et al., ""J.Br.Nucl.Energy Soc"".,vol.16,161 (1977). Adjusted by : J. G. Williams.Procedings of the consultants' meeting on delayed neutron properties, Vienna, INDC(NDS)-107/G, 1979." | |
232 | 235-U | Thermal | 0.0156 ± 0.0010 | Reported by: S. Synetos and J. G. Williams.Procedings of the consultants' meeting on delayed neutron properties, Vienna, 1979, | ||
233 | 235-U | 3.1 | 0.0172 ± 0.0013 | Reported by: C. F. Masters, et al., Nucl. Sci. Eng., 36, 202, 1969. | ||
234 | 235-U | 14.9 | 0.0091 ± 0.0004 | Reported by:Evans A.E. et al. Nucl. Sci. Eng., 1973, v. 50, p. 80. | ||
235 | 235-U | 14.9 | 0.0091 ± 0.0004 | Reported by: C. F. Masters, M.M. Thrope, and D.B. Smith, Nucl. Sci. Eng., 36, 202, (1969) | ||
236 | 235-U | 14.9 | 0.0098 ± 0.0008 | Reported by: G.R.Keepin, Rep. LA-4227-MS, Los Alamos scientific laboratory, 1969, p. 17; LA-4320-MC, 1969. | ||
237 | 235-U | 1.165 | 0.01709 ± 0.00082 | Reported by: V.M. Piksaikin et al., Conf. Proc., Nucl. Data for Science and Technology, Bologna, Vol. 59, 1997, pp. 485-487. | ||
238 | 235-U | 0.34 ± 0.07 | 0.0163 ± 0.0006 | Reported by: V.M. Piksaikin et al.,. Yad. Fiz. (in Russia), 1999, v. 62, No. 6, pp. 1-9; Phys. Atomic. Nuclei., v.62,1279 (1999) (in English). | ||
239 | 235-U | 0.59 ± 0.08 | 0.0164 ± 0.0007 | |||
240 | 235-U | 0.81 ± 0.09 | 0.0171 ± 0.0008 | |||
241 | 235-U | 1.01 ± 0.10 | 0.0158 ± 0.0010 | |||
242 | 235-U | 3.23 ± 0.15 | 0.0158 ± 0.0010 | |||
243 | 235-U | 3.75 ± 0.14 | 0.0159 ± 0.0010 | |||
244 | 235-U | 4.20 ± 0.17 | 0.0143 ± 0.0009 | |||
245 | 235-U | 4.72 ± 0.21 | 0.0139 ± 0.0009 | |||
246 | 235-U | fast (En ~ Fission spectrum) | 0.0163 ± 0.0008 | Reported by: D. J. Loaiza et al., Nuclear Science and Engineering, Vol. 128, No. 3, 1998, pp. 270-277. | ||
247 | 235-U | fast (En~144 keV) | 0.0159 ± 0.0004 | Reported by: H.H. Saleh et al., Nuclear Science and Engeneering, vol. 125, No 1, pp. 51-60. | ||
248 | 235-U | fast (En~144 keV) | 0.0167 ± 0.0008 | Reported by: W.S. Charlton, et al., Conf. Proc. Vol. 59. Nucl. Data for Science and Technology, Bologna, 1997, pp. 491-493. | ||
249 | 235-U | thermal | 0.0167 ± 0.0007 | Reported by: R.W. Waldo, et al., Phys. Rev., C, V. 23, No. 3, 1981. | ||
250 | 235-U | thermal | 0.0162 | Reported by: A. D'Angelo, J.L. Rowlands, Progress in Nuclear Energy, Vol. 41. No. 1-4, pp. 391-412, 2002. | ||
251 | 235-U | fast | 0.0163 | |||
252 | 235-U * | less than 4.0 | 0.01668 ± 0.00070 | "Reported by: Cox S. A. , ""Delayed Neutron Data - Review and Evaluation,"" ANL/NDM-5, Argonne National Laboratory (1974)." | ||
253 | 235-U * | 4.0-7.0 | 0.0129 ± 0.0007 | |||
254 | 235-U * | 7.0-20.0 | 0.0090 ± 0.0010 | |||
255 | 235-U * | thermal | 0.01621 ± 0.00050 | Reported by: R.J. Tuttle, Procedings of the consultants' meeting on delayed neutron properties, Vienna, 26-30 March 1979. INDC(NDS)-107/G+Special. pp. 29-67, 1979 | ||
256 | 235-U * | fast | 0.01673 ± 0.00036 | |||
257 | 235-U * | thermal | 0.0165 ± 0.0002 | Reported by: Y. KANEKO, F. AKINO, T. YAMANE, NUCLEAR SCIENCE and TECHNOLOGY, 25[9], pp. 673-681 (September 1988). | ||
258 | 235-U * | thermal | 0.0162 | Reported by: A. D'Angelo, J.L. Rowlands, Progress in Nuclear Energy, Vol. 41. No. 1-4, pp. 391-412, 2002. | ||
259 | 235-U * | fast | 0.0163 | |||
235-U | Photofission | |||||
260 | 235-U | 15 | 0.0096 ± 0.0013 | Reported by: O. P. Nikotin and K. A. Petrzhak, Soviet At. Energy, 20, 268 (1966). | ||
261 | 235-U | 8 -1 3 | 0.0102 ± 0.0008 | Reported by: J. T. Caldwell and E. J. Dowdy, Nucl. Sci. Eng., 56, 179 (1975). | ||
262 | 235-U | 6.67 | 0.0090 ± 0.0008 | Reported by: Caldwell J. T., Dowdy E. J., Nucl. Sci. Eng., 1975, v. 56, 179. | ||
263 | 235-U | 7.7 | 0.0088 ± 0.0008 | |||
264 | 235-U | 7.81 | 0.0113 ± 0.0007 | |||
265 | 235-U | 8.86 | 0.0112 ± 0.0008 | |||
236-U | Neutron induced fission | |||||
266 | 236-U | 1.01 ± 0.10 | 0.0218 ± 0.0022 | Reported by: Piksaikin V.M., Egorov A.S., Mitrofanov K.V., Report INDC(NDS) - 0646, 2013, IAEA, Vienna, Austria. | ||
267 | 236-U | 3.23 ± 0.15 | 0.0233 ± 0.0012 | |||
268 | 236-U | 3.75 ± 0.14 | 0.0232 ± 0.0012 | |||
269 | 236-U | 4.20 ± 0.17 | 0.0218 ± 0.0011 | |||
270 | 236-U | 4.72 ± 0.21 | 0.0220 ± 0.0011 | |||
236-U | Photofission | |||||
271 | 236-U | 8 -1 3 | 0.0160 ± 0.0013 | Reported by: J. T. Caldwell and E. J. Dowdy, Nucl. Sci. Eng. 56, 179 (1975). | ||
272 | 236-U | 6.66 | 0.0143 ± 0.0014 | Reported by: Caldwell J. T., Dowdy E. J. - Nucl. Sci. Eng., 1975, v. 56, 179. | ||
273 | 236-U | 7.63 | 0.0173 ± 0.0012 | |||
274 | 236-U | 8.86 | 0.0164 ± 0.0010 | |||
238-U | Neutron induced fission | |||||
275 | 238-U | 14.0 max | 0.08 ± 0.03 | Reported by: K.H.Sun et al., Phys.Rev.,vol.79,3(1950). | ||
276 | 238-U | 2.7 | 0.0463 ± 0.0071 | Reported by: Brunson G.S. et al., Nucl. Sci. Eng., v.1, p.174 (1956). Adjusted by R.J. Tuttle, 1979. | ||
277 | 238-U | 3 | 0.037 ± 0.004 | 0.0386 ± 0.0052 | Reported by: H. Rose and R. D. Smith, J. Nucl. Energy vol.1, 4, 133 (1957). Adjusted by R.J. Tuttle, 1979. | |
278 | 238-U | 3 | 0.037 ± 0.004 | 0.0367 ± 0.0025 | Reported by: H. Rose and R. D. Smith, J. Nucl. Energy vol.1, 4, 133 (1957). Adjusted by: Cox, 1974. | |
279 | 238-U | 3.01 | 0.0412 ± 0.0017 | 0.0421 ± 0.0043 | Reported by: G. R. Keepin, T. F. Wimett, and R. K. Zeigler, J. Nucl. Energy, 6, 1 (1957); also, Phys. Rev. 107, 1044 (1957). Adjusted by R.J. Tuttle, 1979. | |
280 | 238-U | 3.01 | 0.0412 ± 0.0025 | Reported by: Keepin G. R., Wimett T. F., and Zeigler R. K. - Phys. Rev., 1957, v. 107, p. 1044 .Adjusted by: Zamyatnin, 1976. | ||
281 | 238-U | 3.01 | 0.0421 ± 0.0025 | Reported by: G. R. Keepin,T. F. Wimett , and R. K. Zeigler, J. Nucl. Energy 6, 1, (1957), and Phys. Rev., 107, 1044, 1957. Adjusted by: Cox, 1974. | ||
282 | 238-U | Thermal | (Reference data) | 0.0173 ± 0.0012 | Reported by: B.P.Maksyutenko, Soviet At.Energ.,vol.7, 943 (1961) translated from Atom.Energ. Vol.7,474 (1959). Adjusted by R.J. Tuttle, 1979. | |
283 | 238-U | 2.4 | 0.0426 ± 0.0027 | |||
284 | 238-U | 3.3 | 0.0404 ± 0.0031 | |||
285 | 238-U | 15 | 0.0752 ± 0.0053 | |||
286 | 238-U | 14 | 0.066 ± 0.017 | Reported by: W.E.McGarry et al., Bull.Am.Phys.Soc.II,vol.5,33 (1960). | ||
287 | 238-U | 14 | 0.022 + 0.003 | 0.0282 ± 0.0040 | "Herrmann G., "" Delayed fission neutrons"", Proc. Panel. Vienna, IAEA, p. 147, (1968). Adjusted by: R.J. Tuttle, 1979." | |
288 | 238-U | 14.7 | 0.0261 ± 0.0028 | Reported by: M.Bucko,Soviet At.Energy, vol.20,187,1966. Adjusted by R.J. Tuttle, 1979. | ||
289 | 238-U | 3.1 | 0.0474 ± 0.0032 | Reported by: C. F. Masters, et al., Nucl. Sci. Eng. 36, 202, 1969. Adjusted by: Evans A.E. et al. Nucl. Sci. Eng., 1973, v. 50, p. 80. | ||
290 | 238-U | 14.9 | 0.0283 ± 0.0013 | |||
291 | 238-U | 3.1 | 0.0484 ± 0.0036 | Reported by: C. F. Masters, et al., Nucl. Sci. Eng. 36, 202, 1969. Adjusted by: Zamyatnin, 1976. | ||
292 | 238-U | 14.9 | 0.0283 ± 0.0013 | 0.0283 ± 0.0013 | ||
293 | 238-U | 3.1 | 0.0484 ± 0.0036 | Reported by: C. F. Masters, M.M. Thrope, and D.B. Smith, Nucl. Sci. Eng. 36, 202, (1969). Adjusted by: Cox, 1974. | ||
294 | 238-U | 14.9 | 0.0283 ± 0.0013 | 0.0283 ± 0.0013 | ||
295 | 238-U | 14.1 | 0.0327 ± 0.0027 | 0.0280 ± 0.0024 | Reported by: G.R. Keepin (editor), LA-4227-MS, Los Alamos Scientific Laboratory (1969). Adjusted by: R.J.Tuttle, 1979. | |
296 | 238-U | 14.9 | 0.0332 ± 0.0027 | 0.0262 ± 0.0022 | ||
297 | 238-U | 14.9 | 0.0332 ± 0.0027 | 0.0270 ± 0.0022 | Reported by: G.R. Keepin (editor), LA-4227-MS, Los Alamos Scientific Laboratory (1969). Adjusted by: Zamyatnin, 1976. | |
298 | 238-U | 14.1 | 0.0327 ± 0.0027 | 0.0271 ± 0.0022 | Reported by: G.R. Keepin (editor), LA-4227-MS, Los Alamos Scientific Laboratory (1969). Adjusted by: Cox, 1974. | |
299 | 238-U | 14.9 | 0.0332 ± 0.0027 | 0.0255 ± 0.0021 | ||
300 | 238-U | 14 | 0.0209 ± 0.0074 | Reported by:Notea A. Israel Atomic Energy Comm. Rep. IA-1190, 1969, p.95. Adjusted by: R.J. Tuttle, 1979. | ||
301 | 238-U | 14.8 | 0.016 ± 0.005 | Reported by: Notea A. Israel Atomic Energy Comm. Rep. IA-1190, 1969, p.95. Adjusted by: Zamyatnin, 1976. | ||
302 | 238-U | 14 | 0.016 ± 0.005 | Reported by: A. Notea, IA-1190, P.95, Israel Atomic Energy Comm. (1969). Adjusted by: Cox, 1974. | ||
303 | 238-U | 14 | 0.0228 + 0.0082 | 0.0277 ± 0.0058 | Reported by: Benedict G. et al., Radiochem. Acta, 1972, Bd 17, #1, S.61. Adjusted by: R.J.Tuttle, 1979. | |
304 | 238-U | 14.8 | 0.0228 + 0.0082 | 0.023 ± 0.004 | Reported by: Benedict G. et al., Radiochem. Acta, 1972, Bd 17, #1, S.61. Adjusted by: Zamyatnin, 1976. | |
305 | 238-U | 14.8 | 0.0228 ± 0.0082 | 0.0228 ± 0.0082 | Reported by: G. Benedict, G. Luthardt and G. Herrmann, Radiochim. Acta 17, 1190 (1972). Adjusted by: Cox, 1974. | |
306 | 238-U | 1.65 | 0.0484 ± 0.0040 | Reported by: Evans A.E. et al. Nucl. Sci. Eng., 1973, v. 50, p. 80. | ||
307 | 238-U | 4 | 0.0484 ± 0.0045 | |||
308 | 238-U | 4.25 | 0.0483 ± 0.0044 | |||
309 | 238-U | 4.5 | 0.0474 ± 0.0043 | |||
310 | 238-U | 4.75 | 0.0482 ± 0.0044 | |||
311 | 238-U | 5.15 | 0.0454 ± 0.0043 | |||
312 | 238-U | 5.35 | 0.0453 ± 0.0043 | |||
313 | 238-U | 5.5 | 0.0429 ± 0.0041 | |||
314 | 238-U | 5.75 | 0.0424 ± 0.0040 | |||
315 | 238-U | 6 | 0.0412 ± 0.0041 | |||
316 | 238-U | 6.3 | 0.0404 ± 0.0039 | |||
317 | 238-U | 6.5 | 0.0395 ± 0.0039 | |||
318 | 238-U | 6.7 | 0.0381 ± 0.0038 | |||
319 | 238-U | 6.9 | 0.0374 ± 0.0039 | |||
320 | 238-U | 0.9 - 2.4 | 0.0406 | 0.0436 ± 0.0028 | Reported by: Cox S.A., Whiting D.E.E. Rep. ANL-7610, 1970, p.45. Adjusted by: R.J. Tuttle, 1979. | |
321 | 238-U | 14.8 | 0.0182 ± 15% | 0.0230 ± .0039 | Reported by:Brown M.G. et al., Radiochem. Acta, 1971, Bd 15, S. 109. Adjusted by: R.J. Tuttle, 1979. | |
322 | 238-U | 14.8 | 0.024 ± 0.005 | Reported by:Brown M.G. et al., Radiochem. Acta, 1971, Bd 15, S. 109. Adjusted by: Zamyatnin, 1976. | ||
323 | 238-U | 2.77 | 0.0492 ± 0.005 | Reported by: CliffordD.A. A compilation and evaluation of experimental data. Rep. AERE-R 6993, 1972. Adjusted by: R.J. Tuttle, 1979 | ||
324 | 238-U | fission spectrum | 0.046 ± 0.003 | Reported by: D.A. Clifford, as reported by M.H. McTaggart in Fast Integral Assembly Newsletter Nos. 19-22, March 1972, and M.H. McTaggart, AWRE, Aldersmaston, personal communication, June 20, 1972. Adjusted by: Zamyatnin, 1976 | ||
325 | 238-U | 2.77 | 0.0492 ± 0.0025 | Reported by: D.A. Clifford, as reported by M.H. McTaggart in Fast Integral Assembly Newsletter Nos. 19-22, March 1972, and M.H. McTaggart, AWRE, Aldersmaston, personal communication, June 20, 1972. Adjusted by: Cox, 1974 | ||
326 | 238-U | 1.97 | 0.0439 ± 0.0026 | "Reported by: S. A. Cox, ""Delayed Neutron Data - Review and Evaluation,"" ANL/NDM-5, Argonne National Laboratory (1974). Adjusted by: Tuttle, 1979" | ||
327 | 238-U | 2.98 | 0.04347 ± 0.00260 | |||
328 | 238-U | 3.98 | 0.04288 ± 0.00260 | |||
329 | 238-U | 1.97 | 0.0439 ± 0.0026 | "Reported by: S. A. Cox, ""Delayed Neutron Data - Review and Evaluation,"" ANL/NDM-5, Argonne National Laboratory (1974). Adjusted by: Cox, 1974" | ||
330 | 238-U | 2.98 | 0.04347 ± 0.00260 | |||
331 | 238-U | 3.98 | 0.04288 ± 0.00260 | |||
332 | 238-U | 2.77 | 0.0439 ± 0.0017 | 0.0445 ± 0.0017 | Reported by: C. B. Besant, et al., J.Br.Nucl.Energy Soc,vol.16,161 (1977). Adjusted by: Tuttle, 1979 | |
333 | 238-U | 0.9 | 0.0437 ± 0.0030 | Reported by: Cox S.A., Whiting D.E.E. Rep. ANL-7610, 1970, p.45. | ||
334 | 238-U | 1 | 0.0039 ± 0.0040 | |||
335 | 238-U | 1.1 | 0.0400 ± 0.0020 | |||
336 | 238-U | 1.2 | 0.0396 ± 0.0020 | |||
337 | 238-U | 1.3 | 0.0375 ± 0.0020 | |||
338 | 238-U | 1.4 | 0.0396 ± 0.0010 | |||
339 | 238-U | 1.5 | 0.0406 ± 0.0010 | |||
340 | 238-U | 1.6 | 0.0406 ± 0.0020 | |||
341 | 238-U | 1.76 | 0.0406 ± 0.0030 | |||
342 | 238-U | 1.85 | 0.0418 ± 0.0025 | |||
343 | 238-U | 2.05 | 0.0425 ± 0.0010 | |||
344 | 238-U | 2.24 | 0.0412 ± 0.0010 | |||
345 | 238-U | 2.43 | 0.0425 ± 0.0025 | |||
346 | 238-U | 1.01 ± 0.10 | 0.0381 ± 0.0018 | Reported by: V.M. Piksaikin et al. Delayed Neutron Yield From Fast Neutron Induced Fission of U-238. Issues of Atomic Science and Technology. Nuclear constants. SSC RF-IPPE, Obninsk, No. 1, pp. 80-86., 2001; V.M. Piksaikin et al. Experimental Studies of the Absolute Total Delayed Neutron Yields From Neutron Induced Fission of U-238 in the Energy Range 1-5 MeV. Progress in Nuclear Energy, 2002, v.41, 1-4, pp.135-144. | ||
347 | 238-U | 3.23 ± 0.15 | 0.0462 ± 0.0025 | |||
348 | 238-U | 3.75 ± 0.14 | 0.0465 ± 0.0012 | |||
349 | 238-U | 4.20 ± 0.17 | 0.0462 ± 0.0020 | |||
350 | 238-U | 4.72 ± 0.21 | 0.0463 ± 0.0012 | |||
351 | 238-U | 4.94 ± 0.20 | 0.0467 ± 0.0023 | |||
352 | 238-U | fast | 0.0460 ± 0.0025 | Reported by: R.W. Waldo, R.A. Karam, R.A. Meyer. Delayed neutron yields: Time dependent measurements and a predictive model. Phys. Rev. C, V. 23, No. 3, 1981. | ||
353 | 238-U | fast | 0.0465 | Reported by: A. D'Angelo, J.L. Rowlands. Conclusions concerning the delayed neutron data for the major actinides. Progress in Nuclear Energy, Vol. 41. No. 1-4, pp. 391-412, 2002. | ||
354 | 238-U * | less than 4.0 | 0.0460 ± 0.0025 | "Reported by: S. A. Cox, ""Delayed Neutron Data - Review and Evaluation,"" ANL/NDM-5, Argonne National Laboratory (1974)." | ||
355 | 238-U * | 4.0-8.0 | 0.0360 ± 0.0025 | |||
356 | 238-U * | 8.0-20.0 | 0.026 ± 0.002 | |||
357 | 238-U * | fast | 0.0439 ± 0.0010 | Reported by: R.J. Tuttle. Delayed-neutron yields in nuclear fission. Procedings of the consultants' meeting on delayed neutron properties, Vienna, 26-30 March 1979. INDC(NDS)-107/G+Special. pp. 29-67, 1979 | ||
358 | 238-U * | fast | 0.0465 | Reported by: A. D'Angelo, J.L. Rowlands. Conclusions concerning the delayed neutron data for the major actinides. Progress in Nuclear Energy, Vol. 41. No. 1-4, pp. 391-412, 2002. | ||
238-U | Photofission | |||||
359 | 238-U | 12. 20 | 0.036 ± 0.008 | Reported by: G. Moscati and J. Goldemberg, Phys. Rev. 126_, 1098 (1962). Adjusted by Tuttle, 1979 | ||
360 | 238-U | 12 | 0.036 ± 0.008 | Reported by: G. Moscati and J. Goldemberg, Phys. Rev., 1962, v. 126, p. 1098.; Adjusted by Zamyatnin, 1976 | ||
361 | 238-U | 15 | 0.031 ± 0.004 | Reported by: O. P. Nikotin and K. A. Petrzhak, Soviet At. Energy, V.20, No.3, 268 (1966).; Adjusted by: Tuttle, 1979 | ||
362 | 238-U | 15 | 0.031 ± 0.004 | Reported by: O.P.Nikotin, K.A. Petrzhak - Atomic Energy, 1966, v.20, No. 3, p.268.; Adjusted by: Zamyatnin, 1976 | ||
363 | 238-U | 8-1 2 | 0.0291 ± 0.0009 | 0.0291 ± 0.0009 | "Reported by: J. T. Caldwell, E. J. Dowdy, and G. M. Worth, ""Physics and Chemistry of Fission 1973,"" Vol. I, p 431, IAEA, Vienna (1974). Adjusted by: Tuttle, 1979" | |
364 | 238-U | 8-1 3 | 0.0291 ± 0.0020 | 0.0291 ± 0.0020 | Reported by: J.T.Caldwell et al., Report LA-UR-74-1208, Los Alamos Scientific Laboratory (1974).; Adjusted by: Tuttle, 1979 | |
365 | 238-U | 6.53 | 0.0306 ± 0.0024 | Reported by: Caldwell J. T., Dowdy E. J. - Nucl. Sci. Eng., 1975, v. 56, 179.; Adjusted by: Zamyatnin, 1976 | ||
366 | 238-U | 7.54 | 0.0276 ± 0.0017 | |||
367 | 238-U | 7.66 | 0.0306 ± 0.0014 | |||
368 | 238-U | 8.88 | 0.0275 ± 0.0019 | |||
238-U | Charged - Particle induced fission | |||||
369 | 238-U | 21.4 (He-3) | 0.012 ± .002 | 0.012 ± .003 | Reported by: E. T. Chulick and P. l. Reeder, Nucl. Phys. , A173, 497 (1971). Adjusted by: Tuttle, 1979 | |
370 | 238-U | 23.3 (He-3) | 0.013 ± .002 | 0.013 ± .003 | ||
371 | 238-U | 28.7 (He-3) | 0.016 ± .003 | 0.016 ± .004 | ||
372 | 238-U | 33.8 (He-3) | 0.007 ± .001 | 0.007 ± .002 | ||
373 | 238-U | 19.8 (He-4) | 0.030 ± .003 | 0.030 ± .004 | ||
374 | 238-U | 24.5 (He-4) | 0.0086 ± .0007 | 0.0086 ± .0008 | ||
375 | 238-U | 28.6 (He-4) | 0.014 ± .002 | 0.014 ± .003 | ||
237-Np | Neutron induced fission | |||||
376 | 237-Np | 1.154 | 0.001141 ± 0.00054 | Reported by: V.M. Piksaikin, Ju. F. Balakshev, S.G. Isaev, L.E. Kazakov, G.G. Korolev, B.D. Kuzminov, N.N. Sergachev, M.Z. Tarasko. Measurements of periods, relative abundances and absolute total yields of delayed neutrons from fast neutron induced fission of 235U and 237Np. Conf. Proc. Vol. 59. Nucl. Data for Science and Technology, Bologna, 1997, pp. 485-487. | ||
377 | 237-Np | 0.34 | 0.01021 ± 0.00020 | Reported by: V.M. Piksaikin et al., Feature of the energy dependence of the total delayed neutron yields for fast neutron induced fission of U-235 and Np-237, Yad. Fiz.(in Russian), v.62, No.6, pp.1-9, 1999. Numerical data in: A.D'Angelo, Overview of the delayed neutron data activities and results monitored by NEA/WPEC subgroup 6, Progress in Nuclear Energy, v.41, No.1-4, pp.5-31, 2002. | ||
378 | 237-Np | 0.59 | 0.00992 ± 0.00035 | |||
379 | 237-Np | 0.81 | 0.01053 ± 0.00021 | |||
380 | 237-Np | 1.01 | 0.01141 ± 0.00025 | |||
381 | 237-Np | 3.23 | 0.01006 ± 0.00022 | |||
382 | 237-Np | 3.74 | 0.00948 ± 0.00019 | |||
383 | 237-Np | 4.2 | 0.00926 ± 0.00019 | |||
384 | 237-Np | 4.72 | 0.00897 ± 0.00018 | |||
385 | 237-Np | 1.5 | 0.0087 | D. Dore et al., 237Np absolute delayed neutron yield measurements. EPJ Web of Conferences 146, 04029 (2017) | ||
386 | 237-Np | 1.964 | 0.0089 | |||
387 | 237-Np | 2.958 | 0.0094 | |||
388 | 237-Np | 4.19 | 0.0075 | |||
389 | 237-Np | 4.983 | 0.0079 | |||
390 | 237-Np | 5.99 | 0.0091 | |||
391 | 237-Np | 7 | 0.0074 | |||
392 | 237-Np | 10 | 0.0074 | |||
393 | 237-Np | 16 | 0.0038 | |||
394 | 237-Np | fast (=144 keV) | 0.0129 ± 0.0004 | Reported by: H.H. Saleh et al., Measurements of delayed neutron constants and fission yields from 235U, 237Np, 241Am, 243Am. Nuclear Science and Engeneering, vol. 125, No 1, pp. 51-60. | ||
395 | 237-Np | thermal | 0.0125 ± 0.0011 | Reported by: S.B. Borzakov. Physics of Atomic Nuclei, Vol. 63, No. 4, 2000, pp. 589-597. | ||
396 | 237-Np | 1.3 | 0.0126 ± 0.0007 | |||
397 | 237-Np | fast (=144 keV) | 0.0114 ± 0.0007 | Reported by: W.S. Charlton, T.A. Parish, S. Raman, N.Shinohara, M. Andoh. Delayed neutron emission measurements from fast fission of U-235, Np-237, Am-243. Conf. Proc. Vol. 59. Nucl. Data for Science and Technology, Bologna, 1997, pp. 491-493. | ||
398 | 237-Np | 1.154 | 0.01212 ± 0.00057 | Absolute value | Reported by: V.M. Piksaikin, Ju. F. Balakshev, S.G. Isaev, L.E. Kazakov, G.G. Korolev, B.D. Kuzminov, N.N. Sergachev, M.Z. Tarasko. Measurements of periods, relative abundances and absolute total yields of delayed neutrons from fast neutron induced fission of 235U and 237Np. Conf. Proc. Nucl. Data for Science and Technology, Bologna, 1997, pp. 485-487. | |
399 | 237-Np | fast (En ~ Fission spectrum) | 0.0126 ± 0.0007 | Reported by: D. J. Loaiza, G. Brunson, R. Sanchez, K. Butterfield. Measurements of Absolute Delayed Neutron Yield and Group Constants in the Fast Fission of 235U and 237Np. Nuclear Science and Engineering, Vol. 128, No. 3, 1998, pp. 270-277. | ||
400 | 237-Np | fast | 0.0107 ± 0.0010 | Reported by: R.W. Waldo, R.A. Karam, R.A. Meyer. Delayed neutron yields: Time dependent measurements and a predictive model. Phys. Rev. C, V. 23, No. 3, 1981. | ||
237-Np | Photofission | |||||
401 | 237-Np | 8 -1 3 | 0.0047 ± 0.0004 | 0.0047 ± 0.0004 | Reported by: J. T. Caldwell and E. J. Dowdy, Nucl. Sci. Eng. 56, 179 (1975).; Adjusted by: Tuttle, 1979 | |
402 | 237-Np | 7.68 | 0.0038 ± 0.0004 | Reported by: Caldwell J. T., Dowdy E. J. - Nucl. Sci. Eng., 1975, v. 56, 179.; Adjusted by: Zamyatnin, 1976 | ||
403 | 237-Np | 9.31 | 0.0050 ± 0.0004 | |||
404 | 237-Np | 9.92 | 0.0054 ± 0.0004 | |||
238-Pu | Neutron induced fission | |||||
405 | 238-Pu | fast | 0.0046 ± 0.0007 | Reported by: R.W. Waldo, R.A. Karam, R.A. Meyer. Delayed neutron yields: Time dependent measurements and a predictive model. Phys. Rev. C, V. 23, No. 3, 1981. | ||
239-Pu | Neutron induced fission | |||||
406 | 239-Pu | Thermal | 0.0076 | Reported by: R.R. Wilson. Letters to the editor. p 560, 1947; Adjusted by: Tuttle, 1979 | ||
407 | 239-Pu | Thermal | β49/β25 = 0.47 ± 0.07 | 0.0090 ± 0.0015 | Reported by: de Hoffmann & Feld, 1947; Adjusted by: R.J. Tuttle, 1979 | |
408 | 239-Pu | Thermal | 0.00604 ± 0.00068 | "Reported by: Brunson et al. ""Nucl. Sci. Eng."", 1956, v.1, p.174; Adjusted by: Tuttle, 1979" | ||
409 | 239-Pu | 0.42 | 0.00692 ± 0.00082 | |||
410 | 239-Pu | thermal | 0.0059 ± 0.0004 | "Reported by: Brunson et al. ""Nucl. Sci. Eng."", 1956, v.1, p.174; Adjusted by: Zamyatnin, 1976" | ||
411 | 239-Pu | 1 | 0.0070 ± 0.0006 | Reported by: H. Rose and R. D. Smith, J. Nucl. Energy, vol.1, 4, 133 (1957). Adjusted by: Tuttle, 1979 | ||
412 | 239-Pu | 1 | 0.0068 ± 0.0004 | Reported by: H. Rose and R. D. Smith, J. Nucl. Energy, vol.1, 4, 133 (1957). Adjusted by: Cox, 1974 | ||
413 | 239-Pu | Thermal | 0.0061 ± 0.0003 | 0.0061 ± 0.0007 | Reported by: G. R. Keepin, T. F. Wimett, and R. K. Zeigler, J. Nucl. Energy, 6, 1, (1957), and Phys. Rev., 107, 1044, 1957.; Adjusted by: Tuttle, 1979 | |
414 | 239-Pu | 1.59 FSCSW | 0.0063 ± 0.0003 | 0.0064 ± 0.0007 | ||
415 | 239-Pu | Thermal | 0.0061 ± 0.0005 | Reported by: Keepin G. R., Wimett T. F., and Zeigler R. K. - Phys. Rev., 1957, v. 107, p. 1044.; Adjusted by: Zamyatnin, 1976 | ||
416 | 239-Pu | 1.59 FSCSW | 0.0063 ± 0.0005 | |||
417 | 239-Pu | thermal | 0.0061 ± 0.0007 | Reported by: G. R. Keepin,T. F. Wimett , and R. K. Zeigler, J. Nucl. Energy, 6, 1, (1957), and Phys. Rev., 107, 1044, 1957. Adjusted by: Cox, 1974. | ||
418 | 239-Pu | 1.58 FSCSW | 0.0064 ± 0.0007 | |||
419 | 239-Pu | 14.5 | 0.0130 ± 0.0015 | 0.0135 ± 0.0016 | ||
420 | 239-Pu | 3.1 | 0.00664 ± 0.00047 | Reported by: Masters C.F. et al. Nucl. Sci. Eng., v. 36, p.202,1969. Adjusted by: Tuttle, 1979. | ||
421 | 239-Pu | 14.9 | 0.0041 ± 0.0002 | 0.0041 ± 0.0002 | ||
422 | 239-Pu | 3.1 | 0.0066 ± 0.0005 | Reported by: C. F. Masters, et al., Nucl. Sci. Eng., 36, 202, 1969.; Revision:Evans A.E. et al. Nucl. Sci. Eng., 1973, v. 50, p. 80., Adjusted by: Zamyatnin, 1976. | ||
423 | 239-Pu | 14.8 | 0.0041 ± 0.0002 | |||
424 | 239-Pu | 3.1 | 0.0066 ± 0.0005 | Reported by: C. F. Masters, M.M. Thrope, and D.B. Smith, Nucl. Sci. Eng., 36, 202, (1969). Adjusted by: Cox, 1974 | ||
425 | 239-Pu | 14.9 | 0.0041 ± 0.0002 | |||
426 | 239-Pu | 14.1 | 1.13 ± 0.10 (a) | 0.00424 ± 0.00038 | Reported by: G.R.Keepin, Rep. LA-4227-MS, Los Alamos scientific laboratory, 1969, p. 17; LA-4320-MC, 1969. Adjusted by Tuttle, 1979 | |
427 | 239-Pu | 14.9 | 1.20 ± 0.11 (a) | 0.00439 ± 0.00041 | ||
428 | 239-Pu | 14.9 | 0.0044 ± 0.0004 | Reported by: Keepin, Rep. LA-4227-MS, 1969, p. 17; LA-4320-MC, 1969. Adjusted by: Zamyatnin, 1976 | ||
429 | 239-Pu | 14.1 | 0.00423 ± 0.00037 | Reported by: G.R. Keepin (editor), LA-4227-MS, Los Alamos Scientific Laboratory (1969). Adjusted by: Cox, 1974 | ||
430 | 239-Pu | 14.9 | 0.00451 ± 0.00041 | |||
431 | 239-Pu | Thermal | 0.0076 ± 0.0032 | Reported by: Notea A. Israel Atomic Energy Comm. Rep. IA-1190, 1969, p.95. Adjusted by: Tuttle, 1979 | ||
432 | 239-Pu | thermal | 0.0050 ± 0.0019 | Reported by: Notea A. Israel Atomic Energy Comm. Rep. IA-1190, 1969, p.95. Adjusted by: Zamyatnin, 1976 | ||
433 | 239-Pu | thermal | 0.00517 ± 0.00200 | Reported by: Notea A. Israel Atomic Energy Comm. Rep. IA-1190, 1969, p.95. Adjusted by: Cox, 1974 | ||
434 | 239-Pu | Thermal | β=0.0023 ± 0.0003 | 0.00661 ± 0.00078 | Reported by: Conant J.F., Palmedo P.F. Nucl. Sci. Eng., 1971, v.44, p. 173. Adjusted by: Tuttle, 1979 | |
435 | 239-Pu | thermal | 0.0066 ± 0.0006 | Reported by: Conant J.F., Palmedo P.F. Nucl. Sci. Eng., 1971, v.44, p. 173.; Adjusted by: Zamyatnin, 1976 | ||
436 | 239-Pu | thermal | 0.0066 ± 0.0006 | Reported by: Conant J.F., Palmeda P.F. Nucl. Sci. Eng., 1971, v.44, p. 173.; Adjusted by: Cox, 1974 | ||
437 | 239-Pu | 0.0 - 1.8 | 0.0062 ± 0.0005 | 0.0062 ± 0.0005 | Reported by: Evans A.E., Thorpe M.M., Krick M.S. - Nucl. Sci. Eng., 1973, v. 50, p. 80; Adjusted by: Tuttle, 1979 | |
438 | 239-Pu | 0.05 | 0.0061 ± 0.0005 | Reported by: Krick M.S. et al., Nucl.Sci.Eng.1972, v.47,p.311, Trans.Amer.Nucl.Soc., 1970,v.13, p.746. Adjusted by: Evans A.E. et al. Nucl. Sci. Eng., 1973, v. 50, p. 80. | ||
439 | 239-Pu | 0.11 | 0.0060 ± 0.0005 | |||
440 | 239-Pu | 0.21 | 0.0060 ± 0.0005 | |||
441 | 239-Pu | 0.32 | 0.0061 ± 0.0005 | |||
442 | 239-Pu | 0.43 | 0.0062 ± 0.0005 | |||
443 | 239-Pu | 0.53 | 0.0063 ± 0.0005 | |||
444 | 239-Pu | 0.64 | 0.00631 ± 0.00050 | |||
445 | 239-Pu | 0.74 | 0.00633 ± 0.00050 | |||
446 | 239-Pu | 0.84 | 0.00624 ± 0.00050 | |||
447 | 239-Pu | 0.94 | 0.00621 ± 0.00050 | |||
448 | 239-Pu | 1.05 | 0.00626 ± 0.00050 | |||
449 | 239-Pu | 1.15 | 0.00626 ± 0.00050 | |||
450 | 239-Pu | 1.25 | 0.00629 ± 0.00050 | |||
451 | 239-Pu | 1.35 | 0.00633 ± 0.00050 | |||
452 | 239-Pu | 1.45 | 0.00633 ± 0.00050 | |||
453 | 239-Pu | 1.55 | 0.00624 ± 0.00050 | |||
454 | 239-Pu | 1.65 | 0.00621 ± 0.00050 | |||
455 | 239-Pu | 1.75 | 0.00626 ± 0.00050 | |||
456 | 239-Pu | 0.96 | 0.00674 ± 0.00043 | 0.00674 ± 0.00043 | "Reported by: S. A. Cox, ""Delayed Neutron Data - Review and Evaluation,"" ANL/NDM-5, Argonne National Laboratory (1974); Adjusted by: Tuttle, 1979" | |
457 | 239-Pu | 1.97 | 0.00669 ± 0.00043 | 0.00669 ± 0.00043 | ||
458 | 239-Pu | 2.98 | 0.00640 ± 0.00043 | 0.00640 ± 0.00043 | ||
459 | 239-Pu | 3.98 | 0.00663 ± 0.00043 | 0.00663 ± 0.00043 | ||
460 | 239-Pu | 0.96 | 0.00674 ± 0.00043 | "Reported by: S. A. Cox, ""Delayed Neutron Data - Review and Evaluation,"" ANL/NDM-5, Argonne National Laboratory (1974)" | ||
461 | 239-Pu | 1.97 | 0.00669 ± 0.00043 | |||
462 | 239-Pu | 2.98 | 0.00640 ± 0.00043 | |||
463 | 239-Pu | 3.98 | 0.00663 ± 0.00043 | |||
464 | 239-Pu | 0.74 | 0.00598 ± 0.00022 | 0.00606 ± 0.00022 | Reported by: C. B. Besant, et al., J.Br.Nucl.Energy Soc.,vol.16,161 (1977); Adjusted by: Tuttle, 1979 | |
465 | 239-Pu | 0.34 ± 0.07 | 0.00651 ± 0.00020 | Reported by: Piksaikin V.M., Egorov A.S., Mitrofanov K.V. The absolute total delayed neutron yields, relative abundances and half-life of delayed neutron groups from neutron induced fission of 232Th, 233U, 236U, 239Pu AND 241Am. Report INDC(NDS) - 0646, 2013, IAEA, Vienna, Austria. | ||
466 | 239-Pu | 0.59 ± 0.08 | 0.00645 ± 0.00009 | |||
467 | 239-Pu | 0.81 ± 0.09 | 0.00643 ± 0.00001 | |||
468 | 239-Pu | 1.01 ± 0.10 | 0.00656 ± 0.00014 | |||
469 | 239-Pu | 3.23 ± 0.15 | 0.00712 ± 0.00033 | |||
470 | 239-Pu | 3.75 ± 0.14 | 0.00704 ± 0.00017 | |||
471 | 239-Pu | 4.20 ± 0.17 | 0.00689 ± 0.00017 | |||
472 | 239-Pu | 4.72 ± 0.21 | 0.00668 ± 0.00019 | |||
473 | 239-Pu | 4.90 ± 0.21 | 0.00608 ± 0.00009 | |||
474 | 239-Pu | thermal | 0.0065 ± 0.0005 | Reported by: R.W. Waldo, R.A. Karam, R.A. Meyer. Delayed neutron yields: Time dependent measurements and a predictive model. Phys. Rev., C, V. 23, No. 3, 1981. | ||
475 | 239-Pu | thermal | 0.00668 ± 0.00023 | Reported by: S.B. Borzakov. Physics of Atomic Nuclei, Vol. 63, No. 4, 2000, pp. 589-597. | ||
476 | 239-Pu * | less than 4.0 | 0.00645 ± 0.00040 | "Reported by: S. A. Cox, ""Delayed Neutron Data - Review and Evaluation,"" ANL/NDM-5, Argonne National Laboratory (1974)" | ||
477 | 239-Pu * | 4.0-7.0 | 0.00538 ± 0.00040 | |||
478 | 239-Pu * | 7.0-20.0 | 0.0043 ± 0.0003 | |||
479 | 239-Pu * | thermal | 0.00628 ± 0.00038 | Reported by: R.J. Tuttle. Delayed-neutron yields in nuclear fission. Procedings of the consultants' meeting on delayed neutron properties, Vienna, 26-30 March 1979. INDC(NDS)-107/G+Special. pp. 29-67, 1979 | ||
480 | 239-Pu * | fast | 0.00630 ± 0.00016 | |||
481 | 239-Pu * | thermal | 0.0065 | Reported by: A. D'Angelo, J.L. Rowlands. Conclusions concerning the delayed neutron data for the major actinides. Progress in Nuclear Energy, Vol. 41. No. 1-4, pp. 391-412, 2002. | ||
482 | 239-Pu * | fast | 0.00651 | |||
239-Pu | Photofission | |||||
483 | 239-Pu | 15 | 0.0036 ± 0.0006 | 0.0036 ± 0.0006 | Reported by: O. P. Nikotin and K. A. Petrzhak, Soviet At. Energy, 20_, 268 (1966). Adjusted by: Tuttle, 1979 | |
484 | 239-Pu | 20 | 0.0036 ± 0.0006 | Reported by: O.P.Nikotin, K.A. Petrzhak - Atomic Energy, 1966, v.20, No. 3, p.268. | ||
485 | 239-Pu | 10.2 - 12 | 0.00372 ± 0.00013 | 0.00372 ± 0.00013 | Reported by J. T. Caldwell, E. J. Dowdy, and G. M. Worth, Physics and Chemistry of Fission 1973, Vol. I, p 431, IAEA, Vienna (1974). Adjusted by: Tuttle, 1979 | |
486 | 239-Pu | 10.2 - 13 | 0.0037 ± 0.0004 | 0.0037 ± 0.0004 | Reported by: Caldwell J. T., Dowdy E. J. - Nucl. Sci. Eng., 1975, v. 56, 179, Adjusted by: Tuttle, 1979 | |
487 | 239-Pu | 7.84 | 0.0037 ± 0.0004 | Reported by: Caldwell J. T., Dowdy E. J. - Nucl. Sci. Eng., 1975, v. 56, 179, Adjusted by: Zamyatnin, 1976 | ||
488 | 239-Pu | 9.65 | 0.0037 ± 0.0004 | |||
240-Pu | Neutron induced fission | |||||
489 | 240-Pu | 2.13 FSCSW | 0.0088 ± 0.0006 | 0.0092 ± 0.0011 | Reported by: G. R. Keepin,T. F. Wimett , and R. K. Zeigler, J. Nucl. Energy, 6, 1, (1957), and Phys. Rev., 107, 1044, 1957; Adjusted by: Tuttle, 1979 | |
490 | 240-Pu | 2.13 FSCSW | 0.0088 ± 0.0009 | Reported by: G. R. Keepin,T. F. Wimett , and R. K. Zeigler, J. Nucl. Energy, 6, 1, (1957), and Phys. Rev., 107, 1044, 1957; Adjusted by: Zamyatnin 1976 | ||
491 | 240-Pu | 2.13 FSCSW | 0.0090 ± 0.0009 | Reported by: G. R. Keepin,T. F. Wimett , and R. K. Zeigler, J. Nucl. Energy, 6, 1, (1957), and Phys. Rev., 107, 1044, 1957; Adjusted by: Cox, 1974 | ||
492 | 240-Pu | 14.1 | 1.49 ± 0.13 (a) | 0.00631 ± 0.00056 | Reported by: G.R.Keepin, Rep. LA-4227-MS, Los Alamos scientific laboratory, 1969, p. 17; LA-4320-MC, 1969; Adjusted by: R.J.Tuttle, 1979. | |
493 | 240-Pu | 14.9 | 1.42 ± 0.12 (a) | 0.00597 ± 0.00051 | ||
494 | 240-Pu | 14.9 | 0.0057 ± 0.0005 | Reported by: G.R. Keepin (editor), LA-4227-MS, Los Alamos Scientific Laboratory (1969); | ||
495 | 240-Pu | 14.1 | 0.0063 ± 0.0009 | |||
496 | 240-Pu | 14.9 | 0.0060 ± 0.0009 | |||
497 | 240-Pu | fast | 0.0090 ± 0.0009 | Reported by: R.W. Waldo, R.A. Karam, R.A. Meyer. Delayed neutron yields: Time dependent measurements and a predictive model. Phys. Rev., C, V. 23, No. 3, 1981. | ||
498 | 240-Pu * | less than 4.0 | 0.0090 ± 0.0009 | "Reported by: S. A. Cox, ""Delayed Neutron Data - Review and Evaluation,"" ANL/NDM-5, Argonne National Laboratory (1974.)" | ||
499 | 240-Pu * | 4.0-7.0 | 0.00758 ± 0.00090 | |||
500 | 240-Pu * | 7.0-20.0 | 0.00615 ± 0.00060 | |||
501 | 240-Pu * | fast | (0.0095 ± 0.0008) | Reported by: R.J. Tuttle. Delayed-neutron yields in nuclear fission. Procedings of the consultants' meeting on delayed neutron properties, Vienna, 26-30 March 1979. INDC(NDS)-107/G+Special. pp. 29-67, 1979. | ||
241-Pu | Neutron induced fission | |||||
502 | 241-Pu | Thermal | 0.0154 ± 0.0015 | 0.0162 ± 0.0016 | "Reported by: S. A. Cox, ""Delayed Neutron Data - Review and Evaluation,"" ANL/NDM-5, Argonne National Laboratory (1974.); Adjusted by: R.J. Tuttle., 1979" | |
503 | 241-Pu | thermal | 0.0154 ± 0.0015 | Reported by: S.A. Cox, Phys. Rev. v.123, 1735 (1961). | ||
504 | 241-Pu | thermal | 0.0157 ± 0.0015 | |||
505 | 241-Pu | 14.1 | 2.06 ± 0.19 (a) | 0.00762 ± 0.00071 | Reported by: G.R.Keepin, Rep. LA-4227-MS, Los Alamos scientific laboratory, 1969, p. 17; LA-4320-MC, 1969. Adjusted by: R.J.Tuttle, 1979 | |
506 | 241-Pu | 14.9 | 1.99 ± 0.18 (a) | 0.00732 ± 0.00067 | ||
507 | 241-Pu | 14.9 | 0.0084 ± 0.0008 | Reported by: Rep. LA-4227-MS, 1969, p. 17; LA-4320-MC, 1969. Adjusted by: Zamyatnin, 1976 | ||
508 | 241-Pu | 14.1 | 0.00853 ± 0.00079 | Reported by: G.R. Keepin (editor), LA-4227-MS, Los Alamos Scientific Laboratory (1969); Adjusted by: Cox, 1974 | ||
509 | 241-Pu | 14.9 | 0.00814 ± 0.00074 | |||
510 | 241-Pu | thermal | 0.0157 ± 0.0015 | Reported by: R.W. Waldo, R.A. Karam, R.A. Meyer. Delayed neutron yields: Time dependent measurements and a predictive model. Phys. Rev., C, V. 23, No. 3, 1981. | ||
511 | 241-Pu * | less than 4.0 | 0.0157 ± 0.0015 | "Reported by: S. A. Cox, ""Delayed Neutron Data - Review and Evaluation,"" ANL/NDM-5, Argonne National Laboratory (1974.)" | ||
512 | 241-Pu * | 4.0-7.0 | 0.0121 ± 0.0015 | |||
513 | 241-Pu * | 7.0-20.0 | 0.0084 ± 0.0006 | |||
514 | 241-Pu * | thermal | (0.0152 ± 0.0011) | Reported by: R.J. Tuttle. Delayed-neutron yields in nuclear fission. Procedings of the consultants' meeting on delayed neutron properties, Vienna, 26-30 March 1979. INDC(NDS)-107/G+Special. pp. 29-67, 1979. | ||
515 | 241-Pu * | fast | (0.0152 ± 0.0011) | |||
242-Pu | Neutron induced fission | |||||
516 | 242-Pu | 0.7 - 1.3 (average) | 0.015 ± 0.005 | 0.015 ± 0.005 | Reported by: Krick M.S. et al., Nucl.Sci.Eng. 1972 ,v.47,p.311, Trans.Amer.Nucl.Soc.,1970,v.13,p.746. Adjusted by: Evans A.E. et al. Nucl. Sci. Eng., 1973, v. 50, p. 80. | |
517 | 242-Pu | 0.64 | 0.0151 ± 0.0045 | |||
518 | 242-Pu | 0.84 | 0.0149 ± 0.0045 | |||
519 | 242-Pu | 1.05 | 0.0153 ± 0.0045 | |||
520 | 242-Pu | 1.25 | 0.016 ± 0.005 | |||
521 | 242-Pu | 0.7 - 1.3 | 0.015 ± 0.005 | Reported by: Evans A.E., Thorpe M.M., Krick M.S. - Nucl. Sci. Eng., 1973, v. 50, p. 80. | ||
522 | 242-Pu | fast | 0.0186 ± 0.0009 | Reported by: R.W. Waldo, R.A. Karam, R.A. Meyer. Delayed neutron yields: Time dependent measurements and a predictive model. Phys. Rev., C, V. 23, No. 3, 1981. | ||
523 | 242-Pu * | fast | (0.0221 ± 0.0026) | Reported by: R.J. Tuttle. Delayed-neutron yields in nuclear fission. Procedings of the consultants' meeting on delayed neutron properties, Vienna, 26-30 March 1979. INDC(NDS)-107/G+Special. pp. 29-67, 1979. | ||
241-Am | Neutron induced fission | |||||
524 | 241-Am | 0.86 | 0.00330 ± 0.00050 | Reported by: Piksaikin V.M., Egorov A.S., Mitrofanov K.V. The absolute total delayed neutron yields, relative abundances and half-life of delayed neutron groups from neutron induced fission of 232Th, 233U, 236U, 239Pu AND 241Am. Report INDC(NDS) - 0646, 2013, IAEA, Vienna, Austria. | ||
525 | 241-Am | 0.96 | 0.00360 ± 0.00054 | |||
526 | 241-Am | 1.01 | 0.00460 ± 0.00069 | |||
527 | 241-Am | 3.85 | 0.00490 ± 0.00074 | |||
528 | 241-Am | 4.85 | 0.00540 ± 0.00082 | |||
529 | 241-Am | fast (=144 keV) | 0.0049 ± 0.0002 | Reported by: H.H. Saleh et al., Measurements of delayed neutron constants and fission yields from 235U, 237Np, 241Am, 243Am. Nuclear Science and Engeneering, vol. 125, No 1, pp. 51-60. | ||
530 | 241-Am | fast | 0.0044 ± 0.0005 | Reported by: R.W. Waldo, R.A. Karam, R.A. Meyer. Delayed neutron yields: Time dependent measurements and a predictive model. Phys. Rev., C, V. 23, No. 3, 1981. | ||
242-AmM | Neutron induced fission | |||||
531 | 242-AmM | thermal | 0.0069 ± 0.0005 | |||
243-Am | Neutron induced fission | |||||
532 | 243-Am | fast (=144 keV) | 0.0084 ± 0.0004 | Reported by: H.H. Saleh et al., Measurements of delayed neutron constants and fission yields from 235U, 237Np, 241Am, 243Am. Nuclear Science and Engeneering, vol. 125, No 1, pp. 51-60. | ||
533 | 243-Am | fast (=144 keV) | 0.0086 ± 0.0005 | Reported by: W.S. Charlton, T.A. Parish, S. Raman, N.Shinohara, M. Andoh. Delayed neutron emission measurements from fast fission of U-235, Np-237, Am-243. Conf. Proc. Vol. 59. Nucl. Data for Science and Technology, Bologna, 1997, pp. 491-493. | ||
245-Cm | Neutron induced fission | |||||
534 | 245-Cm | thermal | 0.0059 ± 0.0004 | Reported by: R.W. Waldo, R.A. Karam, R.A. Meyer. Delayed neutron yields: Time dependent measurements and a predictive model. Phys. Rev., C, V. 23, No. 3, 1981. | ||
249-Cf | Neutron induced fission | |||||
535 | 249-Cf | thermal | 0.0027 ± 0.0002 | |||
252-Cf | Spontaneous Fission | |||||
536 | 252-Cf | Thermal | 0.0086 ± 0.0010 | 0.0086 ± 0.0010 | Reported by: S.A.Cox, Phys. Rev.,v.123,p.1735(1958); Proc. of 2nd Geneva conferece, v.15,p.392(1958) | |
537 | 252-Cf | Thermal | 0.0086 ± 0.0010 | Reported by: R.W. Waldo, R.A. Karam, R.A. Meyer. Delayed neutron yields: Time dependent measurements and a predictive model. Phys. Rev., C, V. 23, No. 3, 1981. |