ENTRY 32633 20100219 31473263300000001 SUBENT 32633001 20100219 31473263300100001 BIB 15 61 3263300100002 TITLE The absolute determination of cumulative yield of 3263300100003 several nuclides from thermal neutron and fission 3263300100004 spectrum neutron induced fission of U-235 3263300100005 AUTHOR (Li Ze) 3263300100006 + Fission yield group 3263300100007 INSTITUTE (3CPRAEP) 3263300100008 REFERENCE (J,HFH,2,(1),1,198002) 3263300100009 SAMPLE The U3O8 powder and metallic uranium were used as 3263300100010 sample respectively, both diameter were 16 mm, the 3263300100011 thickness was 0.2 mm for metallic uranium sample, the 3263300100012 isotope component for both sample were as follows : 3263300100013 U-234 1.1% 3263300100014 U-235 90.2% 3263300100015 U-236 0.3% 3263300100016 U-238 8.4% 3263300100017 FACILITY (REAC) Heavy-water reactor 3263300100018 INC-SOURCE Thermal neutrons from the horizontal hole of reactor. 3263300100019 The neutron flux at the sample was about 1.0 x 10**5 3263300100020 neutrons/cm2/sec. The fission spectrum neutron was 3263300100021 produced by a convertor which was made of metallic 3263300100022 uranium foil (90% for U-235,diameter 66 cm, weight 3263300100023 150 grams) and irradiated by the thermal neutron beam. 3263300100024 METHOD (CHSEP) 3263300100025 First,fission products were separated from the 3263300100026 irradiated samples by radiochemistry method and 3263300100027 weighed for the determination of the chemical yield. 3263300100028 Then the gamma rays or beta particle from fission 3263300100029 products were measured by using gamma 3263300100030 spectrometer or beta measurement device respectively. 3263300100031 DETECTOR (FISCH) A double fission ionization chamber was used 3263300100032 for measuring the fission rate of thick target. 3263300100033 (NAICR) two Nai(Tl) single channel spectrometers were 3263300100034 used for measuring the gamma rays from Mo-99 (Mo-99 to 3263300100035 Tc-99m balance system). 3263300100036 (GEMUC) two low-background beta devices were used for 3263300100037 measuring the beta particles from Zr-95,Ce-144 and 3263300100038 Nd-147. All devices have been calibrated by using 3263300100039 different gamma and beta sources respectively. 3263300100040 MONITOR Absolute measurement 3263300100041 DECAY-DATA No information given 3263300100042 CORRECTION The following corrections have been made: 3263300100043 . 2-3% for extrapolating to zero discrimination 3263300100044 threshold of pulse amplitude discrimination curve. 3263300100045 . 2-3% for fission fragments self-absorption in 3263300100046 the U-235 sample. 3263300100047 . 0.1-1% for counting loss of counting system. 3263300100048 . 1-2% for neutron flux stability during the 3263300100049 irradiating period. 3263300100050 . 0.3% for contribution of other isotopes 3263300100051 fission. 3263300100052 ERR-ANALYS (DATA-ERR) The total errors were given, it consists of 3263300100053 . random error due to thermal neutrons or fission 3263300100054 spectrum neutrons 3263300100055 . systematic error due to weight of thickness uranium 3263300100056 target, fission rate measurement error and device 3263300100057 efficiency calibration error 3263300100058 STATUS (TABLE) Data taken from Table 3 and 5 of j,HFH,vol.2, 3263300100059 No.1,p.1,1980 for thermal and fission spectrum neutron 3263300100060 respectively. 3263300100061 HISTORY (19951125C) Compiled by Liang Qichang, CNDC. 3263300100062 (20100219A) SD:Updated to new date formats,lower case. 3263300100063 ENDBIB 61 0 3263300100064 NOCOMMON 0 0 3263300100065 ENDSUBENT 64 0 3263300199999 SUBENT 32633002 20100219 31473263300200001 BIB 1 1 3263300200002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW) 3263300200003 ENDBIB 1 0 3263300200004 COMMON 1 3 3263300200005 EN-MEAN 3263300200006 EV 3263300200007 0.0253 3263300200008 ENDCOMMON 3 0 3263300200009 DATA 4 3 3263300200010 ELEMENT MASS DATA DATA-ERR 3263300200011 NO-DIM NO-DIM PC/FIS PC/FIS 3263300200012 40. 95. 6.39 0.21 3263300200013 42. 99. 6.08 0.16 3263300200014 58. 144. 5.34 0.34 3263300200015 ENDDATA 5 0 3263300200016 ENDSUBENT 15 0 3263300299999 SUBENT 32633003 20100219 31473263300300001 BIB 1 1 3263300300002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,FIS) 3263300300003 ENDBIB 1 0 3263300300004 COMMON 1 3 3263300300005 EN-MEAN 3263300300006 MEV 3263300300007 1.8 3263300300008 ENDCOMMON 3 0 3263300300009 DATA 4 6 3263300300010 ELEMENT MASS DATA DATA-ERR 3263300300011 NO-DIM NO-DIM PC/FIS PC/FIS 3263300300012 40. 95. 6.53 0.27 3263300300013 42. 99. 6.38 0.18 3263300300014 44. 103. 3.36 0.18 3263300300015 44. 106. 0.638 0.045 3263300300016 58. 144. 5.28 0.24 3263300300017 60. 147. 2.36 0.11 3263300300018 ENDDATA 8 0 3263300300019 ENDSUBENT 18 0 3263300399999 ENDENTRY 3 0 3263399999999