ENTRY 21755 20230517 231721755 0 1 SUBENT 21755001 20230517 231721755 1 1 BIB 12 43 21755 1 2 TITLE The value of eta for U-238 with neutrons 21755 1 3 of energy between 12 MeV and 19 MeV 21755 1 4 AUTHOR (P.H.White) 21755 1 5 REFERENCE (J,JNE/AB,16,261,1962) 21755 1 6 INSTITUTE (2UK ALD) 21755 1 7 FACILITY (VDG,2UK ALD) 3 MV Van der Graaff 21755 1 8 INC-SOURCE (D-T) 5 cm long tritium gas target. 21755 1 9 For neutron source inside uranium shell- 21755 1 10 600 keV deuterons at a current of 30 microAmps 21755 1 11 for neutron detector inside uranium shell- 21755 1 12 3 MeV deuterons at a current of 7 to 8 microAmps 21755 1 13 SAMPLE Two uranium shells of thickness 2.04 cm and 4.08 cm. 21755 1 14 Isotopic composition measured by mass spectrometer. 21755 1 15 METHOD Neutron multiplication and transmission measured 21755 1 16 at one energy with the uranium shell surrounding 21755 1 17 the neutron source. 21755 1 18 Neutron multiplication measured at a series 21755 1 19 of energies with the uranium shell surrounding the 21755 1 20 detector. 21755 1 21 Eta values obtained from a two energy group analysis. 21755 1 22 DETECTOR (SCIN) Xenon gas scintillator with Pu-239 deposited 21755 1 23 on the detector walls. 21755 1 24 (LONGC) 21755 1 25 (SCIN) proton recoil plastic scintillator were used 21755 1 26 to monitor the neutron flux from the source. 21755 1 27 CORRECTION .Background thermal neutrons. 21755 1 28 .Neutrons produced in the target by reactions 21755 1 29 other than d-t. 21755 1 30 .Neutron scattering within and between the two 21755 1 31 energy groups by structural material. 21755 1 32 .Variation of neutron flux across uranium shells. 21755 1 33 .Alpha particle background in fission detector. 21755 1 34 .Photomultiplier background. 21755 1 35 .Target contamination. 21755 1 36 .Geometric effects, including finite counter 21755 1 37 size and counter absorption. 21755 1 38 .Isotopic composition of uranium sample and 21755 1 39 fissile material in the fission counters. 21755 1 40 ERR-ANALYS (DATA-ERR) No information about source of uncertainty 21755 1 41 HISTORY (19820129C) A.P.T. 21755 1 42 (19820915C) A.P.T. Main reference corrected 21755 1 43 (20230517A) SD:Updated to new date formats,lower case. 21755 1 44 Corrections in all Subents. 21755 1 45 ENDBIB 43 0 21755 1 46 NOCOMMON 0 0 21755 1 47 ENDSUBENT 46 0 21755 199999 SUBENT 21755002 20230517 231721755 2 1 BIB 3 3 21755 2 2 REACTION (92-U-238(N,NON),,ETA) 21755 2 3 STATUS (TABLE) Tbl.4 from J.Nucl.En.,AB16(1962)261 21755 2 4 HISTORY (20230517A) SD: Data units corrected. 21755 2 5 ENDBIB 3 0 21755 2 6 NOCOMMON 0 0 21755 2 7 DATA 3 6 21755 2 8 EN DATA DATA-ERR 21755 2 9 MEV PRT/REAC PRT/REAC 21755 2 10 12.6 3.07 0.19 21755 2 11 14.4 3.34 0.15 21755 2 12 15.6 4.36 0.40 21755 2 13 16.8 3.98 0.23 21755 2 14 17.8 4.12 0.25 21755 2 15 18.8 4.11 0.22 21755 2 16 ENDDATA 8 0 21755 2 17 ENDSUBENT 16 0 21755 299999 SUBENT 21755003 20230517 231721755 3 1 BIB 6 18 21755 3 2 REACTION (92-U-238(N,INL)92-U-238,,SIG,,,DERIV) 21755 3 3 ASSUMED (ASSUM1,92-U-238(N,NON),,SIG) For 14.2 MeV neutrons 21755 3 4 taken from A.V.Cohen, see REL-REF. 21755 3 5 (ASSUM2,92-U-238(N,2N)92-U-237,,SIG) for 14.2 MeV 21755 3 6 neutrons interpolated from J.L.Perkin+, see REL-REF. 21755 3 7 (ASSUM3,92-U-238(N,F),,NU) for 14.2 MeV neutrons 21755 3 8 taken from J.L.Perkin+, see REL-REF. 21755 3 9 (ASSUM4,92-U-238(N,F),,SIG) for 14.2 MeV neutrons 21755 3 10 REL-REF (R,21211001,A.V.Cohen,J,JNE/AB,14,180,1961) -ASSUM1 21755 3 11 (R,21208001,J.L.Perkin+,J,JNE/AB,14,69,1961) -ASSUM2 21755 3 12 (R,21252001,A.Moat+,J,JNE/AB,15,102,1961) -ASSUM3 21755 3 13 ANALYSIS Data was calculated using an interpolated value 21755 3 14 for eta from Subent 002 and the following assumed 21755 3 15 values. 21755 3 16 STATUS (TABLE) Text on p.270 of J.Nucl.En.,AB16(1962)261 21755 3 17 (DEP,21755002) Eta value 21755 3 18 HISTORY (20230517A) SD: SF9=DERIV added to REACTION code. 21755 3 19 Data units corrected. COMMENT -> ANALYSIS. 21755 3 20 ENDBIB 18 0 21755 3 21 COMMON 7 6 21755 3 22 ASSUM1 ASSUM1-ERR ASSUM2 ASSUM3 ASSUM3-ERR ASSUM4 21755 3 23 ASSUM4-ERR 21755 3 24 B B B NO-DIM NO-DIM NO-DIM 21755 3 25 NO-DIM 21755 3 26 2.89 0.05 0.75 4.44 0.12 1.13 21755 3 27 0.02 21755 3 28 ENDCOMMON 6 0 21755 3 29 DATA 3 1 21755 3 30 EN DATA DATA-ERR 21755 3 31 MEV B B 21755 3 32 14.2 0.10 0.19 21755 3 33 ENDDATA 3 0 21755 3 34 ENDSUBENT 33 0 21755 399999 SUBENT 21755004 20230517 231721755 4 1 BIB 6 18 21755 4 2 REACTION (92-U-238(N,3N)92-U-236,,SIG,,,DERIV) 21755 4 3 ASSUMED (ASSUM1,92-U-238(N,NON),,SIG) For 14.2 MeV neutrons 21755 4 4 taken from A.V.Cohen, see REL-REF. 21755 4 5 (ASSUM2,92-U-238(N,2N)92-U-237,,SIG) for 14.2 MeV 21755 4 6 neutrons interpolated from J.L.Perkin+, see REL-REF. 21755 4 7 (ASSUM3,92-U-238(N,F),,NU) for 14.2 MeV neutrons 21755 4 8 taken from A.Moat+, see REL-REF. 21755 4 9 (ASSUM4,92-U-238(N,F),,SIG) for 14.2 MeV neutrons 21755 4 10 REL-REF (R,21211001,A.V.Cohen,J,JNE/AB,14,180,1961) -ASSUM1 21755 4 11 (R,21208001,J.L.Perkin+,J,JNE/AB,14,69,1961) -ASSUM2 21755 4 12 (R,21252001,A.Moat+,J,JNE/AB,15,102,1961) -ASSUM3 21755 4 13 ANALYSIS Data was calculated using an interpolated value 21755 4 14 for eta from Subent 002 and the following assumed 21755 4 15 values. 21755 4 16 STATUS (TABLE) Text on p.270 of J.Nucl.En.,AB16(1962)261 21755 4 17 (DEP,21755002) Eta value 21755 4 18 HISTORY (20230517A) SD: SF9=DERIV added to REACTION code. 21755 4 19 Data units corrected. COMMENT -> ANALYSIS. 21755 4 20 ENDBIB 18 0 21755 4 21 COMMON 7 6 21755 4 22 ASSUM1 ASSUM1-ERR ASSUM2 ASSUM3 ASSUM3-ERR ASSUM4 21755 4 23 ASSUM4-ERR 21755 4 24 B B B NO-DIM NO-DIM NO-DIM 21755 4 25 NO-DIM 21755 4 26 2.89 0.05 0.75 4.44 0.12 1.13 21755 4 27 0.02 21755 4 28 ENDCOMMON 6 0 21755 4 29 DATA 3 1 21755 4 30 EN DATA DATA-ERR 21755 4 31 MEV B B 21755 4 32 14.2 0.89 0.20 21755 4 33 ENDDATA 3 0 21755 4 34 ENDSUBENT 33 0 21755 499999 ENDENTRY 4 0 2175599999999