ENTRY 21202 20230516 23172120200000001 SUBENT 21202001 20230516 23172120200100001 BIB 10 35 2120200100002 TITLE Measurements of the energy dependence of the fission 2120200100003 neutron yield per neutron absorbed in Pu-239 and 2120200100004 U-235 in the range 0.006-0.36 eV 2120200100005 AUTHOR (H.M.Skarsgard,C.J.Kenward) 2120200100006 REFERENCE (J,JNE,6,212,1958) 2120200100007 (R,AERE-R/R-2267,1958) 2120200100008 INSTITUTE (2UK HAR) 2120200100009 FACILITY (REAC,2UK HAR) BEPO reactor at AERE 2120200100010 (SPECC,2UK HAR) K-Cl crystal spectrometer. 2120200100011 (SELVE,2UK HAR) Mechanical velocity selector in 2120200100012 conjunction with the crystal spectrometer for neutron 2120200100013 energies below 0.05 eV to eliminate higher order 2120200100014 neutrons from the diffracted beam. 2120200100015 SAMPLE Disc of fissile material of sufficient thickness to 2120200100016 almost totally absorb the incident beam. 2120200100017 METHOD Detection of fission neutrons. 2120200100018 DETECTOR (BF3) 16 BF-3 counters embedded in paraffin wax 2120200100019 placed symmetrically around the sample. Efficiency 2120200100020 for fast neutrons about 0.3% inside of detector coated 2120200100021 with B2-O3 to absorb slow neutrons scattered from the 2120200100022 sample. BF-3 counter to monitor flux above 0.05 eV. 2120200100023 (PROPC) B-10 foil proportional counter to monitor 2120200100024 flux below 0.05 eV. 2120200100025 CORRECTION Corrections for- 2120200100026 departure of monitor counter response from 1/V law. 2120200100027 Scattering and absorption by canning material and 2120200100028 isotopic impurities in the sample. 2120200100029 Transmission of fissile samples. 2120200100030 Counting losses due to scaler dead time. 2120200100031 Higher order contamination of the neutron beam. 2120200100032 Cross-sections from BNL-325 used to make the 2120200100033 corrections. 2120200100034 HISTORY (19791205T) 2120200100035 (20230516A) SD:Updated to new date formats,lower case. 2120200100036 Corrections in all Subents. 2120200100037 ENDBIB 35 0 2120200100038 NOCOMMON 0 0 2120200100039 ENDSUBENT 38 0 2120200199999 SUBENT 21202002 20230516 23172120200200001 BIB 3 4 2120200200002 REACTION (92-U-235(N,ABS),,ETA) 2120200200003 STATUS (NDD) From NEUDADA. 2120200200004 Graphical data on fig.4 of the J.Nucl.En.,6(1958)212. 2120200200005 HISTORY (20230516A) SD: Data units updated (NO-DIM -> PRT/REAC)2120200200006 ENDBIB 4 0 2120200200007 NOCOMMON 0 0 2120200200008 DATA 2 8 2120200200009 EN DATA 2120200200010 EV PRT/REAC 2120200200011 6.00E-03 2.065 2120200200012 7.80E-03 2.08 2120200200013 1.00E-02 2.06 2120200200014 1.30E-02 2.11 2120200200015 1.80E-02 2.08 2120200200016 2.53E-02 2.08 2120200200017 3.50E-02 2.08 2120200200018 5.00E-02 2.08 2120200200019 ENDDATA 10 0 2120200200020 ENDSUBENT 19 0 2120200299999 SUBENT 21202003 20230516 23172120200300001 BIB 3 4 2120200300002 REACTION (92-U-235(N,ABS),,ALF) 2120200300003 STATUS (NDD) From NEUDADA. Data absent in the 2120200300004 J.Nucl.En.,6(1958)212 and in the AERE-R/R-2267,1958. 2120200300005 HISTORY (20230516U) SD: BIB updated. 2120200300006 ENDBIB 4 0 2120200300007 NOCOMMON 0 0 2120200300008 DATA 2 8 2120200300009 EN DATA 2120200300010 EV NO-DIM 2120200300011 6.0000E-03 1.8300E-01 2120200300012 7.8000E-03 1.7400E-01 2120200300013 1.0000E-02 1.8500E-01 2120200300014 1.3000E-02 1.5700E-01 2120200300015 1.8000E-02 1.7400E-01 2120200300016 2.5300E-02 1.7400E-01 2120200300017 3.5000E-02 1.7400E-01 2120200300018 5.0000E-02 1.7400E-01 2120200300019 ENDDATA 10 0 2120200300020 ENDSUBENT 19 0 2120200399999 SUBENT 21202004 20230516 23172120200400001 BIB 3 4 2120200400002 REACTION (94-PU-239(N,ABS),,ETA) 2120200400003 STATUS (NDD) From NEUDADA. 2120200400004 Graphical data on fig.2 of the J.Nucl.En.,6(1958)212. 2120200400005 HISTORY (20230516A) SD: Data units updated (NO-DIM -> PRT/REAC)2120200400006 ENDBIB 4 0 2120200400007 NOCOMMON 0 0 2120200400008 DATA 2 17 2120200400009 EN DATA 2120200400010 EV PRT/REAC 2120200400011 7.00E-03 2.076 2120200400012 1.00E-02 2.095 2120200400013 1.26E-02 2.115 2120200400014 1.75E-02 2.085 2120200400015 2.30E-02 2.082 2120200400016 3.00E-02 2.06 2120200400017 4.00E-02 2.055 2120200400018 5.00E-02 2.01 2120200400019 6.00E-02 1.972 2120200400020 7.40E-02 1.925 2120200400021 9.00E-02 1.88 2120200400022 1.10E-01 1.833 2120200400023 1.35E-01 1.785 2120200400024 1.60E-01 1.705 2120200400025 2.10E-01 1.65 2120200400026 2.80E-01 1.63 2120200400027 3.60E-01 1.675 2120200400028 ENDDATA 19 0 2120200400029 ENDSUBENT 28 0 2120200499999 ENDENTRY 4 0 2120299999999