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