ENTRY 14278 20140417 14011427800000001 SUBENT 14278001 20140417 14011427800100001 BIB 10 52 1427800100002 TITLE Investigation of the prompt-neutron spectrum for 1427800100003 spontaneously- fissioning 252Cf 1427800100004 AUTHOR (V.P.Poenitz,T.Tamura) 1427800100005 INSTITUTE (1USAANL,2JPNTOH) 1427800100006 REFERENCE (C,82ANTWER,,465,1982) 1427800100007 SAMPLE 252Cf deposit on a 0.0254 cm thick platinum 1427800100008 disc of 0.953 cm diameter. The source strength was 1427800100009 1.43E+5 fissions per second 1427800100010 DETECTOR (SCIN)A gas-scintillation counter was used for the 1427800100011 detection of fission events. The detector has a 1427800100012 cylindrical shape with 16 cm height and a diameter 1427800100013 of 22 cm. Neutron entry and exit windows with a 1427800100014 radius of 13 cm at the top and bottom of the counter 1427800100015 consisted of 0.0O36 cm thick Al foil. A mixture of 85% 1427800100016 argon and 15% nitrogen was used as the scintillation 1427800100017 gas. Four photo- multipliers were mounted on the 1427800100018 outside of the cylindrical surface. 1427800100019 (SCIN) Two liquid scintillation detectors with NE213 1427800100020 scintillator were used as black neutron detectors (BND)1427800100021 Smaller scintillator with a radius of 7.62 cm 1427800100022 and a height of 17.78 cm, and with a cylindrical 1427800100023 neutron-entrance channel of 1.9 cm radius and 4.76 cm 1427800100024 length was coupled to RCA 8854 photomultiplier. The 1427800100025 larger BND was a cylindrical liquid scintillator with 1427800100026 a radius of 10 cm and a height of 37 cm, and with a 1427800100027 neutron entrance channel of 1.9 cm radius and 14 cm 1427800100028 length coupled to four 58 DVP phototubes. 1427800100029 Gas scintillation detector with 252Cf source was 1427800100030 placed in a 4pi neutron shield built with lithium 1427800100031 and boron plastic blocks. Neutrons were colimated by 1427800100032 sophisticated series of collimators and after the 1427800100033 flight path of 2.58/3.47 m detected by small/big 1427800100034 scintillation counter. Several shadow bars and carbon 1427800100035 samples were used to determine background and total C 1427800100036 cross section for normalization purposes. 1427800100037 METHOD (TOF,PSD) Time of flight was used to determine 1427800100038 neutron energy. Pulse shape discrimination 1427800100039 properties of NE2123 scintillator was used to 1427800100040 discriminate against gamma rays from CF source 1427800100041 CORRECTION Experiment was designed in such way as to minimize 1427800100042 necessary corrections. Data were corrected for 1427800100043 - accidental coincidences 1427800100044 - shadow bar background 1427800100045 - residual background between gamma peak and neutrons1427800100046 - dead time losses in stop channel 1427800100047 - total fission fragment absorption (5%) 1427800100048 - elastic scattering of neutrons in Pt backing 1427800100049 - neutron backscattering to the BND (1%) 1427800100050 ERR-ANALYS (DATA-ERR) No information given, probably total 1427800100051 uncertainty given. 1427800100052 HISTORY (20101015C) Compiled by S.H. 1427800100053 (20140417U) SD: Page of ref. 82ANTWER corrected. 1427800100054 ENDBIB 52 0 1427800100055 NOCOMMON 0 0 1427800100056 ENDSUBENT 55 0 1427800199999 SUBENT 14278002 20101015 13681427800200001 BIB 3 4 1427800200002 REACTION (98-CF-252(0,F),PR,NU/DE,,MXD) 1427800200003 STATUS (CURVE) Data taken from fig. 10 of the reference 1427800200004 ANALYSIS Data are given as ratio of the experimental spectrum 1427800200005 to a Maxwellian distribution with T = 1.42 MeV 1427800200006 ENDBIB 4 0 1427800200007 COMMON 1 3 1427800200008 KT-NRM 1427800200009 MEV 1427800200010 1.42 1427800200011 ENDCOMMON 3 0 1427800200012 DATA 3 52 1427800200013 E DATA DATA-ERR 1427800200014 MEV NO-DIM NO-DIM 1427800200015 0.246 0.911 0.031 1427800200016 0.294 0.956 0.027 1427800200017 0.343 0.961 0.026 1427800200018 0.391 0.940 0.024 1427800200019 0.441 0.976 0.026 1427800200020 0.490 0.978 0.023 1427800200021 0.538 0.976 0.022 1427800200022 0.585 0.955 0.020 1427800200023 0.587 0.956 0.022 1427800200024 0.633 0.976 0.022 1427800200025 0.681 0.982 0.029 1427800200026 0.731 0.972 0.030 1427800200027 0.780 0.982 0.028 1427800200028 0.829 0.962 0.024 1427800200029 0.874 0.971 0.026 1427800200030 0.926 0.981 0.026 1427800200031 0.973 0.992 0.024 1427800200032 1.018 1.011 0.021 1427800200033 1.118 1.001 0.019 1427800200034 1.214 0.994 0.020 1427800200035 1.317 0.994 0.021 1427800200036 1.404 1.017 0.017 1427800200037 1.499 1.027 0.020 1427800200038 1.597 1.016 0.018 1427800200039 1.697 1.027 0.018 1427800200040 1.785 1.030 0.022 1427800200041 1.883 1.037 0.020 1427800200042 1.981 1.037 0.022 1427800200043 2.077 1.031 0.019 1427800200044 2.173 1.042 0.024 1427800200045 2.269 1.041 0.020 1427800200046 2.366 1.047 0.023 1427800200047 2.456 1.064 0.022 1427800200048 2.559 1.043 0.026 1427800200049 2.646 1.056 0.026 1427800200050 2.740 1.057 0.026 1427800200051 2.855 1.033 0.025 1427800200052 2.941 1.050 0.020 1427800200053 3.189 1.011 0.022 1427800200054 3.418 1.019 0.024 1427800200055 3.670 1.004 0.028 1427800200056 3.917 0.970 0.022 1427800200057 4.401 1.015 0.026 1427800200058 4.890 1.011 0.036 1427800200059 5.382 0.980 0.038 1427800200060 5.908 0.979 0.046 1427800200061 6.390 0.972 0.050 1427800200062 6.862 1.000 0.060 1427800200063 7.355 0.917 0.098 1427800200064 7.838 0.946 0.109 1427800200065 8.301 1.089 0.132 1427800200066 9.041 1.045 0.163 1427800200067 ENDDATA 54 0 1427800200068 ENDSUBENT 67 0 1427800299999 SUBENT 14278003 20101015 13681427800300001 BIB 3 5 1427800300002 REACTION (98-CF-252(0,F),PR,NU/DE,,MXD) 1427800300003 STATUS (CURVE) Data taken from fig. 11 of the reference 1427800300004 ANALYSIS Data are given as ratio of the experimental spectrum 1427800300005 to a Maxwellian distribution with the same average 1427800300006 energy of 2.159 MeV 1427800300007 ENDBIB 5 0 1427800300008 COMMON 1 3 1427800300009 KT-NRM 1427800300010 MEV 1427800300011 2.159 1427800300012 ENDCOMMON 3 0 1427800300013 DATA 3 51 1427800300014 E DATA DATA-ERR 1427800300015 MEV NO-DIM NO-DIM 1427800300016 0.247 0.925 0.031 1427800300017 0.297 0.970 0.029 1427800300018 0.347 0.975 0.028 1427800300019 0.394 0.953 0.025 1427800300020 0.447 0.988 0.024 1427800300021 0.495 0.990 0.025 1427800300022 0.543 0.987 0.021 1427800300023 0.589 0.965 0.020 1427800300024 0.642 0.985 0.020 1427800300025 0.692 0.992 0.029 1427800300026 0.739 0.981 0.029 1427800300027 0.790 0.990 0.029 1427800300028 0.837 0.970 0.024 1427800300029 0.888 0.978 0.029 1427800300030 0.937 0.987 0.027 1427800300031 0.986 0.997 0.026 1427800300032 1.037 1.015 0.020 1427800300033 1.135 1.005 0.017 1427800300034 1.236 0.997 0.019 1427800300035 1.337 0.996 0.019 1427800300036 1.434 1.017 0.018 1427800300037 1.532 1.026 0.020 1427800300038 1.631 1.013 0.017 1427800300039 1.729 1.024 0.018 1427800300040 1.833 1.027 0.024 1427800300041 1.929 1.032 0.020 1427800300042 2.029 1.031 0.021 1427800300043 2.126 1.024 0.021 1427800300044 2.228 1.033 0.022 1427800300045 2.325 1.031 0.021 1427800300046 2.427 1.038 0.027 1427800300047 2.524 1.053 0.021 1427800300048 2.624 1.030 0.026 1427800300049 2.739 1.042 0.025 1427800300050 2.826 1.042 0.025 1427800300051 2.927 1.018 0.024 1427800300052 3.031 1.033 0.020 1427800300053 3.265 0.992 0.021 1427800300054 3.516 0.997 0.021 1427800300055 3.757 0.980 0.027 1427800300056 3.983 0.944 0.025 1427800300057 4.512 0.984 0.027 1427800300058 5.013 0.974 0.035 1427800300059 5.483 0.939 0.036 1427800300060 5.974 0.933 0.041 1427800300061 6.459 0.923 0.048 1427800300062 6.983 0.945 0.059 1427800300063 7.432 0.862 0.091 1427800300064 7.973 0.886 0.101 1427800300065 8.586 1.014 0.121 1427800300066 9.318 0.968 0.153 1427800300067 ENDDATA 53 0 1427800300068 ENDSUBENT 67 0 1427800399999 ENDENTRY 3 0 1427899999999