ENTRY            32793   20190622                             31903279300000001 
SUBENT        32793001   20190622                             31903279300100001 
BIB                 14         77                                 3279300100002 
TITLE      Mass distributions of 22.0 MeV neutron-induced         3279300100003 
           fission of 238U                                        3279300100004 
AUTHOR     (Liu Yonghui,Yang Yi,Feng Jing,Bao Jie,Li Ze,Qi Bujia, 3279300100005 
           Tang Hongqing,Zhou Zuying,Cui Anzhi,Ruan Xichao,       3279300100006 
           Sun Hongqing,Zhang Shengdong,Guo Jingru)               3279300100007 
INSTITUTE  (3CPRAEP)                                              3279300100008 
REFERENCE  (P,INDC(CPR)-056,2,2001)                               3279300100009 
FACILITY   (VDGT,3CPRAEP) The HI-13 Tandem                        3279300100010 
INC-SOURCE (D-T) The tritium gas chamber was used to produce      3279300100011 
           neutrons by the bombardment with the deuteron beam.    3279300100012 
SAMPLE     Natural uranium metal disks of 1.6 cm diameter X 0.05  3279300100013 
           cm thickness with an average weight of about 1.5 g,    3279300100014 
           packed in 0.2 mm thickness pure aluminium foil.        3279300100015 
DETECTOR   (HPGE) A HPGe-92X Spectrum Master of gamma-            3279300100016 
           spectrometer. The resolution of the 120 cm3 HPGe       3279300100017 
           detector was 1.85 keV (FWHM) for the 1.33 MeV gamma    3279300100018 
           ray of Co-60.                                          3279300100019 
           (FISCH) The sample sandwiched between two              3279300100020 
           standardized thin samples was mounted in a double      3279300100021 
           fission chamber, which covered with Cd of 1 mm         3279300100022 
           thickness. The efficiency of the fission chamber was   3279300100023 
           checked by 197Au(n,g) 198Au reaction with thermal      3279300100024 
           neutrons.                                              3279300100025 
METHOD     (TOF) Time of flight technique was used to measure     3279300100026 
           the neutron spectrum.                                  3279300100027 
           (GSPEC) Fission product activities were measured by    3279300100028 
           HPGe gamma-ray spectrometry. Four samples were         3279300100029 
           irradiated for a period varying from 0.5 to 30 h at a  3279300100030 
           distance of about 5 cm from the neutron source in the  3279300100031 
           direction of zero degree.                              3279300100032 
           (ABSFY) Fission rate was monitored by fission chamber. 3279300100033 
DECAY-DATA (35-BR-84-G,31.8MIN,DG,881.2,0.42)                     3279300100034 
           (36-KR-85-M,268.8MIN,DG,304.9,0.140)                   3279300100035 
           (36-KR-87,76.3MIN,DG,402.6,0.496)                      3279300100036 
           (36-KR-88,170.4MIN,DG,196.3,0.2558)                    3279300100037 
           (37-RB-89,15.15MIN,DG,1248.1,0.4257)                   3279300100038 
           (38-SR-91,577.8MIN,DG,555.6,0.615)                     3279300100039 
           (38-SR-92,162.6MIN,DG,1384.1,0.90)                     3279300100040 
           (39-Y-93-G,610.8MIN,DG,266.9,0.073)                    3279300100041 
           (39-Y-94,18.7MIN,DG,918.8,0.56)                        3279300100042 
           (40-ZR-95,92189.MIN,DG,756.7,0.5446)                   3279300100043 
           (40-ZR-97,1014.MIN,DG,742.7,0.9306)                    3279300100044 
           (42-MO-99,3956.7MIN,DG,739.5,0.1214)                   3279300100045 
           (43-TC-101,14.2MIN,DG,306.5,0.88)                      3279300100046 
           (44-RU-103,56526.MIN,DG,497.1,0.909)                   3279300100047 
           (43-TC-104,18.3MIN,DG,358.,0.89)                       3279300100048 
           (44-RU-105,266.4MIN,DG,724.2,0.473)                    3279300100049 
           (47-AG-112,187.8MIN,DG,617.5,0.435)                    3279300100050 
           (48-CD-115-G,3208.3MIN,DG,336.3,0.501)                 3279300100051 
           (51-SB-127,5544.MIN,DG,473.2,0.256)                    3279300100052 
           (50-SN-128-G,59.1MIN,DG,482.,0.59)                     3279300100053 
           (53-I-131,11577.6MIN,DG,637.,0.0717)                   3279300100054 
           (52-TE-132,4694.4MIN,DG,228.3,0.882)                   3279300100055 
           (53-I-133-G,1248.MIN,DG,529.8,0.87)                    3279300100056 
           (53-I-134-G,52.6MIN,DG,847.1,0.954)                    3279300100057 
           (53-I-135,394.2MIN,DG,1131.5,0.2274)                   3279300100058 
           (55-CS-138-G,33.41MIN,DG,1435.8,0.763)                 3279300100059 
           (56-BA-140,18354.MIN,DG,537.3,0.2439)                  3279300100060 
           (56-BA-141,18.27MIN,DG,190.3,0.46)                     3279300100061 
           (57-LA-142,91.1MIN,DG,641.3,0.474)                     3279300100062 
           (58-CE-143,1980.MIN,DG,293.3,0.428)                    3279300100063 
           (59-PR-146,24.15MIN,DG,453.9,0.48)                     3279300100064 
           (60-ND-147,15811.2MIN,DG,531.,0.131)                   3279300100065 
CORRECTION Corrections were made for the gamma self-absorption,   3279300100066 
           gamma geometry, gamma cascade coincidence losses and   3279300100067 
           fission induced by background neutrons.                3279300100068 
ERR-ANALYS (DATA-ERR) Uncertainties (1 sigma) of the yields were  3279300100069 
           obtained by consideration of all known sources of      3279300100070 
           systematic and random errors such as mass              3279300100071 
           determination of standard sample, detector efficiency  3279300100072 
           of HPGe spectra system, statistic error of gamma-ray   3279300100073 
           peak area, and corrections, with the usual rules of    3279300100074 
           error propagation. Uncertainties of decay data are     3279300100075 
           not included.                                          3279300100076 
STATUS     (TABLE) Data were obtained from TABLE 2 of             3279300100077 
           P,INDC(CPR)-056,2,2001                                 3279300100078 
HISTORY    (20190622C) Compiled by Liu Lile (CNDC)                3279300100079 
ENDBIB              77          0                                 3279300100080 
COMMON               1          3                                 3279300100081 
EN                                                                3279300100082 
MEV                                                               3279300100083 
22.0                                                              3279300100084 
ENDCOMMON            3          0                                 3279300100085 
ENDSUBENT           84          0                                 3279300199999 
SUBENT        32793002   20190622                             31903279300200001 
BIB                  1          1                                 3279300200002 
REACTION   (92-U-238(N,F)MASS,CHN,FY)                             3279300200003 
ENDBIB               1          0                                 3279300200004 
NOCOMMON             0          0                                 3279300200005 
DATA                 3         32                                 3279300200006 
MASS       DATA       DATA-ERR                                    3279300200007 
NO-DIM     PC/FIS     PC/FIS                                      3279300200008 
        84.       0.79      0.108                                 3279300200009 
        85.       1.63      0.096                                 3279300200010 
        87.       1.90      0.041                                 3279300200011 
        88.       2.67      0.052                                 3279300200012 
        89.       3.68      0.107                                 3279300200013 
        91.       3.58      0.019                                 3279300200014 
        92.       3.94      0.017                                 3279300200015 
        93.       4.21      0.237                                 3279300200016 
        94.       3.99      0.058                                 3279300200017 
        95.       5.81      0.089                                 3279300200018 
        97.       6.09      0.180                                 3279300200019 
        99.       5.99      0.103                                 3279300200020 
       101.       5.03      0.083                                 3279300200021 
       103.       4.02      0.024                                 3279300200022 
       104.       3.67      0.093                                 3279300200023 
       105.       3.32      0.025                                 3279300200024 
       112.       1.63      0.016                                 3279300200025 
       115.       1.41      0.040                                 3279300200026 
       127.       1.78      0.024                                 3279300200027 
       128.       2.06      0.865                                 3279300200028 
       131.       3.96      0.073                                 3279300200029 
       132.       4.31      0.053                                 3279300200030 
       133.       5.69      0.021                                 3279300200031 
       134.       6.04      0.178                                 3279300200032 
       135.       6.03      0.232                                 3279300200033 
       138.       4.76      0.126                                 3279300200034 
       140.       4.05      0.044                                 3279300200035 
       141.       3.81      0.213                                 3279300200036 
       142.       3.52      0.070                                 3279300200037 
       143.       3.64      0.019                                 3279300200038 
       146.       2.18      0.129                                 3279300200039 
       147.       1.75      0.140                                 3279300200040 
ENDDATA             34          0                                 3279300200041 
ENDSUBENT           40          0                                 3279300299999 
ENDENTRY             2          0                                 3279399999999