ENTRY 33009 20210407 32003300900000001 SUBENT 33009001 20210407 32003300900100001 BIB 11 51 3300900100002 TITLE Charge distribution in low energy fission of actinides 3300900100003 AUTHOR (H.Naik, R.J.Singh, R.H.Iyer) 3300900100004 INSTITUTE (3INDTRM) Radiochemistry Division 3300900100005 REFERENCE (J,JP/G,30,107,2004) 3300900100006 METHOD (REC,GSPEC) Recoiling fission products from 3300900100007 electrodeposited source of 244-Cm on a platinum 3300900100008 planchet were collected for 2 h to 400 h on a 75 mm 3300900100009 thick Lexan polycarbonate foil. 3300900100010 The irradiated solutions or Lexan catcher foils were 3300900100011 used for direct gamma-ray spectrometry. 3300900100012 DETECTOR (HPGE) The irradiated solutions or Lexan catcher 3300900100013 foils as the case may be were counted on a 120 cm3 3300900100014 HPGe detector coupled to a 4K channel analyser in 3300900100015 live time mode, to determine the various fission 3300900100016 product activities. 3300900100017 The resolution of the detector system was 1.8 keV at 3300900100018 1332.0 keV and the dead time was always kept less 3300900100019 than 10%. 3300900100020 ANALYSIS The photopeak areas of different gamma rays of the 3300900100021 nuclides of present interest were calculated by 3300900100022 subtracting the linear Compton background from their 3300900100023 total peak areas. 3300900100024 From the photopeak areas, the cumulative and 3300900100025 independent yields of fission products relative to 3300900100026 some internal fission product monitors were 3300900100027 determined using decay-growth equations. 3300900100028 For long and short-lived fission products, 92-Sr and 3300900100029 104-Tc were used as fission rate monitors 3300900100030 respectively. 3300900100031 The cumulative yields of fission products in the 3300900100032 thermal neutron-induced fission of 232-U and 238-Pu 3300900100033 as well as in spontaneous fission of 244-Cm were 3300900100034 converted to their fraction yields using the mass 3300900100035 chain yields. 3300900100036 The fractional cumulative yields (FCY) of a few 3300900100037 fission products were determined from the activities 3300900100038 of the daughter products using a parent-daughter 3300900100039 genetic equation. 3300900100040 REL-REF (R,,E.Browne+,B,BROWNE,,,1986) 3300900100041 Decay data used in the present work 3300900100042 (R,,J.Blachot+,J,APH,6,3,1982) 3300900100043 Decay data used in the present work 3300900100044 ERR-ANALYS (DATA-ERR) The uncertainties shown on FCY values are 3300900100045 the propagated errors due to errors on cumulative 3300900100046 yields and mass chain yields where as the 3300900100047 uncertainties quoted in the independent yields are 3300900100048 the standard deviations of replicate measurements. 3300900100049 STATUS (APRVD) Approved by Dr.H.Naik, RCD, BARC 3300900100050 HISTORY (20100310C) Paresh Prajapati and S.Mukherjee 3300900100051 (20120703U) On. ANALYSIS: Code AREA deleted 3300900100052 (20210407A) On. Major revisions in 002-004. 3300900100053 ENDBIB 51 0 3300900100054 NOCOMMON 0 0 3300900100055 ENDSUBENT 54 0 3300900199999 SUBENT 33009002 20210407 32003300900200001 BIB 5 6 3300900200002 REACTION (92-U-232(N,F)ELEM/MASS,CUM,FY,,FRC) 3300900200003 FACILITY (REAC,3INDTRM) Research reactor APSARA of BARC 3300900200004 SAMPLE Nitrate solutions of 232U (1.0 ug) sealed in 3300900200005 polypropylene tubes 3300900200006 STATUS (TABLE) Table 1 of J.Phys.G 30(2004)107 3300900200007 HISTORY (20210407A) On. REACTION corrected. 3300900200008 ENDBIB 6 0 3300900200009 COMMON 1 3 3300900200010 EN-DUMMY 3300900200011 EV 3300900200012 0.0253 3300900200013 ENDCOMMON 3 0 3300900200014 DATA 4 24 3300900200015 ELEMENT MASS DATA DATA-ERR 3300900200016 NO-DIM NO-DIM NO-DIM NO-DIM 3300900200017 50. 128. 0.690 0.050 3300900200018 50. 130. 0.213 0.049 3300900200019 51. 129. 0.948 0.087 3300900200020 51. 130. 0.813 0.068 3300900200021 51. 131. 0.548 0.069 3300900200022 51. 132. 0.286 0.031 3300900200023 51. 133. 0.130 0.030 3300900200024 52. 131. 0.978 0.068 3300900200025 52. 133. 0.791 0.050 3300900200026 52. 134. 0.538 0.039 3300900200027 53. 133. 0.9982 0.0163 3300900200028 53. 134. 0.956 0.039 3300900200029 53. 135. 0.739 0.015 3300900200030 53. 136. 0.400 0.056 3300900200031 54. 136. 0.96 0.035 3300900200032 54. 137. 0.786 0.033 3300900200033 54. 138. 0.591 0.065 3300900200034 55. 138. 0.904 0.022 3300900200035 55. 140. 0.640 0.040 3300900200036 56. 140. 0.982 0.019 3300900200037 56. 141. 0.917 0.057 3300900200038 56. 142. 0.892 0.103 3300900200039 58. 146. 0.944 0.009 3300900200040 58. 148. 0.540 0.040 3300900200041 ENDDATA 26 0 3300900200042 ENDSUBENT 41 0 3300900299999 SUBENT 33009003 20210407 32003300900300001 BIB 5 6 3300900300002 REACTION (94-PU-238(N,F)ELEM/MASS,CUM,FY,,FRC) 3300900300003 FACILITY (REAC,3INDTRM) Research reactor APSARA of BARC 3300900300004 SAMPLE Nitrate solutions of 238Pu (5.0 ug) sealed in 3300900300005 polypropylene tube 3300900300006 STATUS (TABLE) Table 1 of J.Phys.G 30(2004)107 3300900300007 HISTORY (20210407A) On. REACTION corrected. 3300900300008 ENDBIB 6 0 3300900300009 COMMON 1 3 3300900300010 EN-DUMMY 3300900300011 EV 3300900300012 0.0253 3300900300013 ENDCOMMON 3 0 3300900300014 DATA 4 24 3300900300015 ELEMENT MASS DATA DATA-ERR 3300900300016 NO-DIM NO-DIM NO-DIM NO-DIM 3300900300017 50. 128. 0.759 0.088 3300900300018 50. 130. 0.208 0.025 3300900300019 51. 129. 0.973 0.013 3300900300020 51. 130. 0.838 0.077 3300900300021 51. 131. 0.511 0.016 3300900300022 51. 132. 0.182 0.017 3300900300023 51. 133. 0.181 0.033 3300900300024 52. 131. 0.970 0.029 3300900300025 52. 132. 0.947 0.036 3300900300026 52. 133. 0.819 0.037 3300900300027 52. 134. 0.511 0.070 3300900300028 53. 134. 0.960 0.060 3300900300029 53. 135. 0.708 0.023 3300900300030 53. 136. 0.466 0.085 3300900300031 54. 136. 0.970 0.030 3300900300032 54. 137. 0.874 0.067 3300900300033 54. 138. 0.598 0.032 3300900300034 55. 138. 0.991 0.048 3300900300035 55. 139. 0.903 0.022 3300900300036 55. 140. 0.607 0.051 3300900300037 56. 141. 0.960 0.041 3300900300038 56. 142. 0.900 0.029 3300900300039 58. 146. 0.936 0.011 3300900300040 58. 148. 0.584 0.124 3300900300041 ENDDATA 26 0 3300900300042 ENDSUBENT 41 0 3300900399999 SUBENT 33009004 20210407 32003300900400001 BIB 4 4 3300900400002 REACTION (96-CM-244(0,F)ELEM/MASS,CUM,FY,,FRC) 3300900400003 SAMPLE Electrodeposited source of 244Cm (96 ug) 3300900400004 STATUS (TABLE) Table 1 of J.Phys.G 30(2004)107 3300900400005 HISTORY (20210407A) On. REACTION corrected. 3300900400006 ENDBIB 4 0 3300900400007 NOCOMMON 0 0 3300900400008 DATA 4 23 3300900400009 ELEMENT MASS DATA DATA-ERR 3300900400010 NO-DIM NO-DIM NO-DIM NO-DIM 3300900400011 50. 128. 0.673 0.083 3300900400012 51. 129. 0.929 0.095 3300900400013 51. 130. 0.785 0.075 3300900400014 51. 131. 0.516 0.018 3300900400015 51. 132. 0.300 0.043 3300900400016 52. 131. 0.973 0.029 3300900400017 52. 132. 0.901 0.044 3300900400018 52. 133. 0.671 0.055 3300900400019 52. 134. 0.548 0.081 3300900400020 53. 134. 0.954 0.088 3300900400021 53. 135. 0.732 0.166 3300900400022 53. 136. 0.400 0.050 3300900400023 54. 135. 0.994 0.084 3300900400024 54. 137. 0.783 0.085 3300900400025 54. 138. 0.464 0.032 3300900400026 55. 138. 0.963 0.060 3300900400027 55. 139. 0.880 0.055 3300900400028 56. 139. 0.998 0.033 3300900400029 56. 141. 0.913 0.073 3300900400030 56. 142. 0.800 0.045 3300900400031 57. 144. 0.890 0.088 3300900400032 58. 146. 0.860 0.086 3300900400033 58. 148. 0.460 0.060 3300900400034 ENDDATA 25 0 3300900400035 ENDSUBENT 34 0 3300900499999 SUBENT 33009005 20100310 31453300900500001 BIB 4 6 3300900500002 REACTION (92-U-232(N,F)ELEM/MASS,IND,FY) 3300900500003 FACILITY (REAC,3INDTRM) Research reactor APSARA of Bhabha 3300900500004 Atomic Research Centre, Trombay, Mumbai 3300900500005 SAMPLE For neutron induced fission, nitrate solutions of 3300900500006 232U (1.0 mu-g) sealed in polypropylene tube was taken.3300900500007 STATUS (TABLE) Data has been taken from Table. 2 3300900500008 ENDBIB 6 0 3300900500009 COMMON 1 3 3300900500010 EN-DUMMY 3300900500011 EV 3300900500012 0.0253 3300900500013 ENDCOMMON 3 0 3300900500014 DATA 4 38 3300900500015 ELEMENT MASS DATA DATA-ERR 3300900500016 NO-DIM NO-DIM PC/FIS PC/FIS 3300900500017 50. 128. 0.974 0.104 3300900500018 50. 129. 0.761 3.4E-02 3300900500019 50. 130. 0.578 1.6E-02 3300900500020 50. 131. 0.158 8.E-03 3300900500021 51. 128. 0.336 2.2E-02 3300900500022 51. 129. 1.217 0.1 3300900500023 51. 130. 1.747 0.122 3300900500024 51. 131. 2.009 0.272 3300900500025 51. 132. 1.369 7.E-02 3300900500026 51. 133. 0.584 0.165 3300900500027 52. 130. 0.65 8.9E-02 3300900500028 52. 131. 1.499 0.165 3300900500029 52. 133. 3.833 5.E-02 3300900500030 52. 134. 2.411 0.226 3300900500031 53. 131. 9.9E-02 8.E-03 3300900500032 53. 132. 0.371 4.1E-02 3300900500033 53. 133. 1.156 9.1E-02 3300900500034 53. 134. 2.32 0.328 3300900500035 53. 135. 3.833 9.7E-02 3300900500036 53. 136. 2.97 0.381 3300900500037 54. 135. 1.67 0.16 3300900500038 54. 136. 4.264 0.267 3300900500039 54. 137. 4.985 0.258 3300900500040 54. 138. 3.973 1.1E-02 3300900500041 55. 136. 0.305 3.8E-02 3300900500042 55. 137. 1.421 0.228 3300900500043 55. 138. 2.005 0.156 3300900500044 55. 140. 3.654 0.429 3300900500045 56. 139. 1.022 0.287 3300900500046 56. 140. 2.629 0.296 3300900500047 56. 141. 3.982 0.132 3300900500048 56. 142. 4.478 0.688 3300900500049 57. 140. 0.139 1.5E-02 3300900500050 57. 146. 0.486 2.2E-02 3300900500051 58. 144. 0.405 6.5E-02 3300900500052 58. 148. 0.493 3.9E-02 3300900500053 59. 146. 0.204 5.8E-02 3300900500054 59. 148. 0.424 3.E-02 3300900500055 ENDDATA 40 0 3300900500056 ENDSUBENT 55 0 3300900599999 SUBENT 33009006 20100310 31453300900600001 BIB 4 6 3300900600002 REACTION (94-PU-238(N,F)ELEM/MASS,IND,FY) 3300900600003 FACILITY (REAC,3INDTRM) Research reactor APSARA of Bhabha 3300900600004 Atomic Research Centre, Trombay, Mumbai 3300900600005 SAMPLE For neutron induced fission, nitrate solution of 3300900600006 238Pu (5.0 mu-g) sealed in polypropylene tube was taken3300900600007 STATUS (TABLE) Data has been taken from Table. 1 3300900600008 ENDBIB 6 0 3300900600009 COMMON 1 3 3300900600010 EN-DUMMY 3300900600011 EV 3300900600012 0.0253 3300900600013 ENDCOMMON 3 0 3300900600014 DATA 4 42 3300900600015 ELEMENT MASS DATA DATA-ERR 3300900600016 NO-DIM NO-DIM PC/FIS PC/FIS 3300900600017 50. 128. 0.621 5.4E-02 3300900600018 50. 129. 0.786 4.E-02 3300900600019 50. 130. 0.577 3.1E-02 3300900600020 50. 131. 0.198 1.6E-02 3300900600021 51. 128. 0.201 3.5E-02 3300900600022 51. 129. 1.144 1.7E-02 3300900600023 51. 130. 1.649 0.144 3300900600024 51. 131. 2.458 2.8E-02 3300900600025 51. 132. 1.307 7.7E-02 3300900600026 51. 133. 0.609 9.E-02 3300900600027 52. 130. 0.418 0.147 3300900600028 52. 131. 2.544 0.147 3300900600029 52. 132. 6.056 4.2E-02 3300900600030 52. 133. 5.637 0.262 3300900600031 52. 134. 3.543 0.467 3300900600032 53. 131. 0.156 4.2E-02 3300900600033 53. 132. 0.452 3.2E-02 3300900600034 53. 133. 1.381 0.182 3300900600035 53. 134. 3.3 0.15 3300900600036 53. 135. 5.502 7.5E-02 3300900600037 53. 136. 2.427 0.212 3300900600038 54. 135. 2.163 0.201 3300900600039 54. 136. 2.667 2.6E-02 3300900600040 54. 137. 3.696 0.37 3300900600041 54. 138. 3.778 4.1E-02 3300900600042 55. 136. 0.161 1.7E-02 3300900600043 55. 137. 0.78 4.1E-02 3300900600044 55. 138. 1.99 3.5E-02 3300900600045 55. 139. 3.455 0.123 3300900600046 55. 140. 2.79 0.238 3300900600047 56. 139. 0.569 5.7E-02 3300900600048 56. 141. 2.469 0.229 3300900600049 56. 142. 3.078 0.175 3300900600050 57. 140. 0.132 2.6E-02 3300900600051 57. 142. 0.5 4.3E-02 3300900600052 57. 144. 1.434 0.435 3300900600053 57. 146. 1.037 0.138 3300900600054 58. 144. 0.148 1.3E-02 3300900600055 58. 146. 0.732 9.8E-02 3300900600056 58. 148. 0.767 3.9E-02 3300900600057 59. 146. 0.6 7.E-02 3300900600058 59. 148. 0.743 0.158 3300900600059 ENDDATA 44 0 3300900600060 ENDSUBENT 59 0 3300900699999 SUBENT 33009007 20100310 31453300900700001 BIB 3 4 3300900700002 REACTION (96-CM-244(0,F)ELEM/MASS,IND,FY) 3300900700003 SAMPLE In the case of spontaneous fission of 244-Cm, 3300900700004 electrodeposited source of 244-Cm (96 mu-g) was taken. 3300900700005 STATUS (TABLE) Data has been taken from Table. 2 3300900700006 ENDBIB 4 0 3300900700007 NOCOMMON 0 0 3300900700008 DATA 4 41 3300900700009 ELEMENT MASS DATA DATA-ERR 3300900700010 NO-DIM NO-DIM PC/FIS PC/FIS 3300900700011 50. 128. 0.441 4.2E-02 3300900700012 50. 129. 0.39 1.E-02 3300900700013 50. 130. 0.237 4.E-02 3300900700014 50. 131. 0.121 1.5E-02 3300900700015 51. 128. 0.201 9.E-03 3300900700016 51. 129. 0.461 6.3E-02 3300900700017 51. 130. 1.352 0.13 3300900700018 51. 131. 1.446 5.E-02 3300900700019 51. 132. 1.216 7.8E-02 3300900700020 51. 133. 0.558 2.6E-02 3300900700021 52. 130. 0.421 1.1E-02 3300900700022 52. 131. 1.482 5.4E-02 3300900700023 52. 132. 2.523 0.185 3300900700024 52. 133. 3.233 0.293 3300900700025 52. 134. 4. 0.534 3300900700026 53. 131. 8.5E-02 9.E-03 3300900700027 53. 132. 0.536 3.4E-02 3300900700028 53. 133. 1.712 0.365 3300900700029 53. 134. 3.353 7.3E-02 3300900700030 53. 135. 4.62 0.597 3300900700031 53. 136. 2.996 0.317 3300900700032 54. 135. 2.02 0.38 3300900700033 54. 136. 4.408 2.3E-02 3300900700034 54. 137. 4.587 0.564 3300900700035 54. 138. 3.406 0.125 3300900700036 55. 137. 1.94 0.581 3300900700037 55. 138. 3.54 0.222 3300900700038 55. 139. 3.941 0.204 3300900700039 56. 139. 0.83 0.225 3300900700040 56. 140. 1.651 0.267 3300900700041 56. 141. 2.883 0.124 3300900700042 56. 142. 2.925 0.218 3300900700043 57. 140. 0.162 4.5E-02 3300900700044 57. 142. 0.809 0.251 3300900700045 57. 144. 1.5 0.23 3300900700046 57. 146. 0.37 0.163 3300900700047 58. 144. 0.404 0.101 3300900700048 58. 146. 1.679 0.264 3300900700049 58. 148. 0.711 6.8E-02 3300900700050 59. 146. 0.359 0.166 3300900700051 59. 148. 0.853 6.6E-02 3300900700052 ENDDATA 43 0 3300900700053 ENDSUBENT 52 0 3300900799999 SUBENT 33009008 20100310 31453300900800001 BIB 4 6 3300900800002 REACTION (92-U-232(N,F)MASS,,ZP) 3300900800003 FACILITY (REAC,3INDTRM) Research reactor APSARA of Bhabha 3300900800004 Atomic Research Centre, Trombay, Mumbai 3300900800005 SAMPLE For neutron induced fission, nitrate solution of 3300900800006 232U (1.0 mu-g) sealed in polypropylene tube was taken.3300900800007 STATUS (TABLE) Data has been taken from Table. 3 3300900800008 ENDBIB 6 0 3300900800009 COMMON 1 3 3300900800010 EN-DUMMY 3300900800011 EV 3300900800012 0.0253 3300900800013 ENDCOMMON 3 0 3300900800014 DATA 3 18 3300900800015 MASS DATA DATA-ERR 3300900800016 NO-DIM NO-DIM NO-DIM 3300900800017 128. 50.35 0.15 3300900800018 129. 50.75 0.2 3300900800019 130. 51.02 0.15 3300900800020 131. 51.4 0.1 3300900800021 132. 51.77 7.E-02 3300900800022 133. 52.1 0.15 3300900800023 134. 52.6 5.E-02 3300900800024 135. 53.16 5.E-02 3300900800025 136. 53.66 0.15 3300900800026 137. 54.05 7.E-02 3300900800027 138. 54.3 0.1 3300900800028 139. 54.81 9.E-02 3300900800029 140. 55.28 8.E-02 3300900800030 141. 55.6 0.12 3300900800031 142. 55.9 0.2 3300900800032 144. 56.6 0.2 3300900800033 146. 57.65 0.6 3300900800034 148. 58.45 0.1 3300900800035 ENDDATA 20 0 3300900800036 ENDSUBENT 35 0 3300900899999 SUBENT 33009009 20100310 31453300900900001 BIB 4 6 3300900900002 REACTION (94-PU-238(N,F)MASS,,ZP) 3300900900003 FACILITY (REAC,3INDTRM) Research reactor APSARA of Bhabha 3300900900004 Atomic Research Centre, Trombay, Mumbai 3300900900005 SAMPLE For neutron induced fission, nitrate solution of 3300900900006 238Pu (5.0 mu-g) sealed in polypropylene tube was taken3300900900007 STATUS (TABLE) Data has been taken from Table. 3 3300900900008 ENDBIB 6 0 3300900900009 COMMON 1 3 3300900900010 EN-DUMMY 3300900900011 EV 3300900900012 0.0253 3300900900013 ENDCOMMON 3 0 3300900900014 DATA 3 18 3300900900015 MASS DATA DATA-ERR 3300900900016 NO-DIM NO-DIM NO-DIM 3300900900017 128. 50.3 0.1 3300900900018 129. 50.62 0.12 3300900900019 130. 50.97 0.2 3300900900020 131. 51.44 5.E-02 3300900900021 132. 51.95 0.1 3300900900022 133. 52.1 6.E-02 3300900900023 134. 52.48 9.E-02 3300900900024 135. 53.14 8.E-02 3300900900025 136. 53.6 0.1 3300900900026 137. 53.85 0.15 3300900900027 138. 54.4 7.E-02 3300900900028 139. 54.77 0.1 3300900900029 140. 55.33 0.1 3300900900030 141. 55.45 0.25 3300900900031 142. 55.75 5.E-02 3300900900032 144. 56.53 8.E-02 3300900900033 146. 57.36 5.E-02 3300900900034 148. 58.35 5.E-02 3300900900035 ENDDATA 20 0 3300900900036 ENDSUBENT 35 0 3300900999999 SUBENT 33009010 20100310 31453300901000001 BIB 3 4 3300901000002 REACTION (96-CM-244(0,F)MASS,,ZP) 3300901000003 SAMPLE In the case of spontaneous fission of 244-Cm, 3300901000004 electrodeposited source of 244-Cm (96 mu-g) was taken. 3300901000005 STATUS (TABLE) Data has been taken from Table. 3 3300901000006 ENDBIB 4 0 3300901000007 NOCOMMON 0 0 3300901000008 DATA 3 18 3300901000009 MASS DATA DATA-ERR 3300901000010 NO-DIM NO-DIM NO-DIM 3300901000011 128. 50.35 0.1 3300901000012 129. 50.83 0.2 3300901000013 130. 51.1 0.15 3300901000014 131. 51.47 7.E-02 3300901000015 132. 51.8 0.1 3300901000016 133. 52.27 8.E-02 3300901000017 134. 52.65 0.1 3300901000018 135. 53.14 0.2 3300901000019 136. 53.7 5.E-02 3300901000020 137. 54.05 0.15 3300901000021 138. 54.45 5.E-02 3300901000022 139. 54.8 0.1 3300901000023 140. 55.07 5.E-02 3300901000024 141. 55.65 0.15 3300901000025 142. 56. 0.15 3300901000026 144. 56.73 0.1 3300901000027 146. 57.8 0.1 3300901000028 148. 58.45 5.E-02 3300901000029 ENDDATA 20 0 3300901000030 ENDSUBENT 29 0 3300901099999 SUBENT 33009011 20100310 31453300901100001 BIB 4 6 3300901100002 REACTION (92-U-232(N,F)ELEM,CHG,FY) 3300901100003 FACILITY (REAC,3INDTRM) Research reactor APSARA of Bhabha 3300901100004 Atomic Research Centre, Trombay, Mumbai 3300901100005 SAMPLE For neutron induced fission, nitrate solution of 3300901100006 232U (1.0 mu-g) sealed in polypropylene tubes was taken3300901100007 STATUS (TABLE) Data has been taken from Table. 4 3300901100008 ENDBIB 6 0 3300901100009 COMMON 1 3 3300901100010 EN-DUMMY 3300901100011 EV 3300901100012 0.0253 3300901100013 ENDCOMMON 3 0 3300901100014 DATA 3 10 3300901100015 ELEMENT DATA DATA-ERR 3300901100016 NO-DIM PC/FIS PC/FIS 3300901100017 50. 2.97 0.37 3300901100018 51. 6.5 0.95 3300901100019 52. 14.65 2.01 3300901100020 53. 12.4 0.66 3300901100021 54. 18.73 1.01 3300901100022 55. 13.77 1.07 3300901100023 56. 19.96 0.57 3300901100024 57. 5.5 0.3 3300901100025 58. 4.62 0.27 3300901100026 59. 1.98 0.36 3300901100027 ENDDATA 12 0 3300901100028 ENDSUBENT 27 0 3300901199999 SUBENT 33009012 20100310 31453300901200001 BIB 4 6 3300901200002 REACTION (94-PU-238(N,F)ELEM,CHG,FY) 3300901200003 FACILITY (REAC,3INDTRM) Research reactor APSARA of Bhabha 3300901200004 Atomic Research Centre, Trombay, Mumbai 3300901200005 SAMPLE For neutron induced fission, nitrate solution of 3300901200006 238Pu (5.0 mu-g) sealed in polypropylene tube was taken3300901200007 STATUS (TABLE) Data has been taken from Table. 4 3300901200008 ENDBIB 6 0 3300901200009 COMMON 1 3 3300901200010 EN-DUMMY 3300901200011 EV 3300901200012 0.0253 3300901200013 ENDCOMMON 3 0 3300901200014 DATA 3 10 3300901200015 ELEMENT DATA DATA-ERR 3300901200016 NO-DIM PC/FIS PC/FIS 3300901200017 50. 2.48 9.E-02 3300901200018 51. 7.61 0.55 3300901200019 52. 19.07 1.43 3300901200020 53. 13.31 1.39 3300901200021 54. 15.27 1.27 3300901200022 55. 12.03 2.2 3300901200023 56. 12.65 2.71 3300901200024 57. 6.41 0.27 3300901200025 58. 4.43 7.E-02 3300901200026 59. 2.71 0.14 3300901200027 ENDDATA 12 0 3300901200028 ENDSUBENT 27 0 3300901299999 SUBENT 33009013 20100310 31453300901300001 BIB 3 4 3300901300002 REACTION (96-CM-244(0,F)ELEM,CHG,FY) 3300901300003 SAMPLE In the case of spontaneous fission of 244-Cm, 3300901300004 electrodeposited source of 244-Cm (96 mu-g) was taken. 3300901300005 STATUS (TABLE) Data has been taken from Table. 4 3300901300006 ENDBIB 4 0 3300901300007 NOCOMMON 0 0 3300901300008 DATA 3 10 3300901300009 ELEMENT DATA DATA-ERR 3300901300010 NO-DIM PC/FIS PC/FIS 3300901300011 50. 2.04 0.18 3300901300012 51. 5.31 0.33 3300901300013 52. 21.28 5.05 3300901300014 53. 13.61 1.79 3300901300015 54. 16.64 1.35 3300901300016 55. 11.25 2.26 3300901300017 56. 12. 0.63 3300901300018 57. 7.46 0.85 3300901300019 58. 6.56 0.8 3300901300020 59. 3.66 0.22 3300901300021 ENDDATA 12 0 3300901300022 ENDSUBENT 21 0 3300901399999 SUBENT 33009014 20100310 31453300901400001 BIB 4 6 3300901400002 REACTION (92-U-232(N,F)ELEM,,AP) 3300901400003 FACILITY (REAC,3INDTRM) Research reactor APSARA of Bhabha 3300901400004 Atomic Research Centre, Trombay, Mumbai 3300901400005 SAMPLE For neutron induced fission, nitrate solution of 3300901400006 232U (1.0 mu-g) sealed in polypropylene tubes was taken3300901400007 STATUS (TABLE) Data has been taken from Table. 5 3300901400008 ENDBIB 6 0 3300901400009 COMMON 1 3 3300901400010 EN-DUMMY 3300901400011 EV 3300901400012 0.0253 3300901400013 ENDCOMMON 3 0 3300901400014 DATA 3 10 3300901400015 ELEMENT DATA DATA-ERR 3300901400016 NO-DIM NO-DIM NO-DIM 3300901400017 50. 128.6 0.21 3300901400018 51. 130.7 0.27 3300901400019 52. 133. 0.17 3300901400020 53. 135.1 8.E-02 3300901400021 54. 137.1 9.E-02 3300901400022 55. 139.5 0.13 3300901400023 56. 142. 6.E-02 3300901400024 57. 143.7 0.11 3300901400025 58. 146. 8.E-02 3300901400026 59. 148. 0.15 3300901400027 ENDDATA 12 0 3300901400028 ENDSUBENT 27 0 3300901499999 SUBENT 33009015 20100310 31453300901500001 BIB 4 6 3300901500002 REACTION (94-PU-238(N,F)ELEM,,AP) 3300901500003 FACILITY (REAC,3INDTRM) Research reactor APSARA of Bhabha 3300901500004 Atomic Research Centre, Trombay, Mumbai 3300901500005 SAMPLE For neutron induced fission, nitrate solution of 3300901500006 238Pu (5.0 mu-g) sealed in polypropylene tube was taken3300901500007 STATUS (TABLE) Data has been taken from Table. 5 3300901500008 ENDBIB 6 0 3300901500009 COMMON 1 3 3300901500010 EN-DUMMY 3300901500011 EV 3300901500012 0.0253 3300901500013 ENDCOMMON 3 0 3300901500014 DATA 3 10 3300901500015 ELEMENT DATA DATA-ERR 3300901500016 NO-DIM NO-DIM NO-DIM 3300901500017 50. 128.9 5.E-02 3300901500018 51. 130.8 0.11 3300901500019 52. 132.6 0.1 3300901500020 53. 134.8 0.12 3300901500021 54. 137.1 0.14 3300901500022 55. 138.8 0.24 3300901500023 56. 141.8 0.11 3300901500024 57. 144.5 9.E-02 3300901500025 58. 146.4 7.E-02 3300901500026 59. 148.2 0.16 3300901500027 ENDDATA 12 0 3300901500028 ENDSUBENT 27 0 3300901599999 SUBENT 33009016 20100310 31453300901600001 BIB 3 4 3300901600002 REACTION (96-CM-244(0,F)ELEM,,AP) 3300901600003 SAMPLE In the case of spontaneous fission of 244-Cm, 3300901600004 electrodeposited source of 244-Cm (96 mu-g) was taken. 3300901600005 STATUS (TABLE) Data has been taken from Table. 5 3300901600006 ENDBIB 4 0 3300901600007 NOCOMMON 0 0 3300901600008 DATA 3 10 3300901600009 ELEMENT DATA DATA-ERR 3300901600010 NO-DIM NO-DIM NO-DIM 3300901600011 50. 128. 0.19 3300901600012 51. 131. 0.1 3300901600013 52. 133.9 0.4 3300901600014 53. 134.9 7.E-02 3300901600015 54. 136.8 0.11 3300901600016 55. 138.6 0.25 3300901600017 56. 141.6 0.21 3300901600018 57. 143.6 0.2 3300901600019 58. 146.2 0.18 3300901600020 59. 148. 0.25 3300901600021 ENDDATA 12 0 3300901600022 ENDSUBENT 21 0 3300901699999 ENDENTRY 16 0 3300999999999