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