ENTRY 22152 20180829 22702215200000001 SUBENT 22152001 20180829 22702215200100001 BIB 16 70 2215200100002 REFERENCE (J,NIM/A,286,220,1990) 2215200100003 REL-REF (R,21981003,P.Geltenbort,C,85SANTA,1,393,1985) Source 2215200100004 of ASSUMED value, see EXFOR 21981003. 2215200100005 TITLE Pulse height defect in an ionization chamber invest- 2215200100006 igated by cold fission measurements. 2215200100007 AUTHOR (G.Simon, J.Trochon, F.Brisard, C.Signarbieux) 2215200100008 INSTITUTE (2FR BRC) G.Simon, J.Trochon, F.Brisard 2215200100009 (2FR SAC) C.Signarbieux and experimental site 2215200100010 FACILITY (REAC,2FR SAC) Saclay reactor ORPHEE. 2215200100011 INC-SOURCE (REAC) 2215200100012 INC-SPECT .Thermal reactor spectrum. 2215200100013 METHOD (PHD) For each analyzed fission event four quantities 2215200100014 are recorded, the anode pulse heights and the electron2215200100015 drift times from each side of the chamber, from which 2215200100016 the fragment mass and energy can be determined 2215200100017 providing that the non-ionizing part of the energy 2215200100018 lost by the fragment (the so-called pulse height 2215200100019 defect) is properly estimated. This was investigated 2215200100020 by considering those fission events for which there 2215200100021 is perfect fragment identification (so-called 'cold' 2215200100022 fission, characterized by high kinetic energy 2215200100023 fragments and no neutron emission). The resulting 2215200100024 pulse height defect was shown to be negligible for 2215200100025 the present configuration, thus the fragment kinetic 2215200100026 energy can be well represented by a linear function 2215200100027 of anode pulse height response. 2215200100028 gas at 450 +-1 mbar pressure, consisting of two back- 2215200100029 to-back gridded chambers separated by a central 2215200100030 cathode at the center of which is located the fissile 2215200100031 sample. Two Frisch grids of 30 micron tungsten wire 2215200100032 screen the anodes from the positive ion effect. The 2215200100033 chamber is operated at constant room temperature, and 2215200100034 the gas filling replenished at a flow rate of 5 l/hr. 2215200100035 The energy resolution was approximately 200 keV for a 2215200100036 100 MeV fragment kinetic energy. 2215200100037 PART-DET (FF) 2215200100038 SAMPLE .A very thin fissile sample is required. The experiment2215200100039 used a sample consisting of UF4 in a layer of 2215200100040 5.3 micro-g/cm**2 evaporated onto a 5 micro-g/cm**2 2215200100041 thick carbon foil backing. 2215200100042 ANALYSIS .The fragment kinetic energy and mass before and after 2215200100043 neutron emission are calculated for each fission 2215200100044 event by an iterative procedure, the mean values and 2215200100045 standard deviations are derived from the resulting 2215200100046 distributions. In these calculations the coefficients 2215200100047 in the linear function relating kinetic energy to 2215200100048 pulse height have been adjusted to reproduce the 2215200100049 ASSUMED value. 2215200100050 ASSUMED (ASSUM,92-U-235(N,F),PRE,AKE,LF+HF) 2215200100051 Total kin.energy before neutron emission. 2215200100052 CORRECTION -The analysis includes neutron emission and backing 2215200100053 effect corrections, the latter to correct for the 2215200100054 energy lost by the fragment that crosses the carbon 2215200100055 foil backing (at zero entrance angle this is about 2215200100056 300 keV compared with the average energy lost in the 2215200100057 fissile deposit of 60 keV, which is negligible). 2215200100058 ERR-ANALYS The accuracy in the assumed value was used to deter- 2215200100059 mine the relative uncertainty in a single absolute 2215200100060 kinetic energy measurement; The uncertainties varied 2215200100061 from DE/E = 3.0E-3 to 4.1E-3 for kinetic energies 2215200100062 ranging from 100 down to 60 MeV. 2215200100063 HISTORY (19900821C) S.W. 2215200100064 (20090216A) M.M. BIB information was added. 2215200100065 Dates were corrected for 4-digits year. 2215200100066 Free text was corrected to be human-readable. 2215200100067 Misprints in ASSUNED were corrected (two brackets were2215200100068 deleted). Second reference C,85SANTA,1,393,1985 was 2215200100069 move in REL-REF. Subents 009-010 were added. 2215200100070 DATA-ERR in Subents 002-008 was corrected into MISC. 2215200100071 (20180829A) SD: REACTION code corrected in Subent 010. 2215200100072 ENDBIB 70 0 2215200100073 COMMON 3 3 2215200100074 EN-DUMMY ASSUM ASSUM-ERR 2215200100075 EV MEV MEV 2215200100076 2.5300E-02 1.7040E+02 4.0000E-01 2215200100077 ENDCOMMON 3 0 2215200100078 ENDSUBENT 77 0 2215200199999 SUBENT 22152002 20090216 22072215200200001 BIB 4 6 2215200200002 REACTION (92-U-235(N,F),PRE,AP,LF,MXW) 2215200200003 MISC-COL (MISC) Standard deviaton. RMS width. 2215200200004 STATUS (TABLE) Data taken from main reference, Table 1 . 2215200200005 (DEP,22152009) 2215200200006 HISTORY (19900821C) S.W. 2215200200007 (19900917E) 2215200200008 ENDBIB 6 0 2215200200009 NOCOMMON 0 0 2215200200010 DATA 2 1 2215200200011 DATA MISC 2215200200012 NO-DIM NO-DIM 2215200200013 9.6270E+01 5.4200E+00 2215200200014 ENDDATA 3 0 2215200200015 ENDSUBENT 14 0 2215200299999 SUBENT 22152003 20090216 22072215200300001 BIB 4 5 2215200300002 REACTION (92-U-235(N,F),SEC,AP,LF,MXW) 2215200300003 MISC-COL (MISC) Standard deviaton. RMS width. 2215200300004 STATUS (TABLE) Data taken from main reference, Table 1 . 2215200300005 HISTORY (19900821C) S.W. 2215200300006 (19900917E) 2215200300007 ENDBIB 5 0 2215200300008 NOCOMMON 0 0 2215200300009 DATA 2 1 2215200300010 DATA MISC 2215200300011 NO-DIM NO-DIM 2215200300012 9.4960E+01 5.3800E+00 2215200300013 ENDDATA 3 0 2215200300014 ENDSUBENT 13 0 2215200399999 SUBENT 22152004 20090216 22072215200400001 BIB 4 5 2215200400002 REACTION (92-U-235(N,F),SEC,AP,HF,MXW) 2215200400003 MISC-COL (MISC) Standard deviaton. RMS width. 2215200400004 STATUS (TABLE) Data taken from main reference, Table 1 . 2215200400005 HISTORY (19900821C) S.W. 2215200400006 (19900917E) 2215200400007 ENDBIB 5 0 2215200400008 NOCOMMON 0 0 2215200400009 DATA 2 1 2215200400010 DATA MISC 2215200400011 NO-DIM NO-DIM 2215200400012 1.3858E+02 4.9700E+00 2215200400013 ENDDATA 3 0 2215200400014 ENDSUBENT 13 0 2215200499999 SUBENT 22152005 20090216 22072215200500001 BIB 4 6 2215200500002 REACTION (92-U-235(N,F),PRE,AKE,LF,MXW) 2215200500003 MISC-COL (MISC) Standard deviaton. RMS width. 2215200500004 STATUS (TABLE) Data taken from main reference, Table 1 . 2215200500005 (DEP,22152010) 2215200500006 HISTORY (19900821C) S.W. 2215200500007 (19900917E) 2215200500008 ENDBIB 6 0 2215200500009 NOCOMMON 0 0 2215200500010 DATA 2 1 2215200500011 DATA MISC 2215200500012 MEV MEV 2215200500013 1.0073E+02 5.0300E+00 2215200500014 ENDDATA 3 0 2215200500015 ENDSUBENT 14 0 2215200599999 SUBENT 22152006 20090216 22072215200600001 BIB 4 7 2215200600002 REACTION (92-U-235(N,F),SEC,AKE,LF,MXW) Average kinetic energy 2215200600003 of post-neutron-emission light fragment. 2215200600004 MISC-COL (MISC) Standard deviaton. RMS width. 2215200600005 STATUS (TABLE) Data taken from main reference, Table 1 . 2215200600006 HISTORY (19900821C) S.W. 2215200600007 (19900917E) 2215200600008 (20090216A) SEC was added in SF5 of Reaction. 2215200600009 ENDBIB 7 0 2215200600010 NOCOMMON 0 0 2215200600011 DATA 2 1 2215200600012 DATA MISC 2215200600013 MEV MEV 2215200600014 9.9360E+01 4.8900E+00 2215200600015 ENDDATA 3 0 2215200600016 ENDSUBENT 15 0 2215200699999 SUBENT 22152007 20090216 22072215200700001 BIB 4 6 2215200700002 REACTION (92-U-235(N,F),PRE,AKE,HF,MXW) 2215200700003 MISC-COL (MISC) Standard deviaton. RMS width. 2215200700004 STATUS (TABLE) Data taken from main reference, Table 1 . 2215200700005 (DEP,22152010) 2215200700006 HISTORY (19900821C) S.W. 2215200700007 (19900917E) 2215200700008 ENDBIB 6 0 2215200700009 NOCOMMON 0 0 2215200700010 DATA 2 1 2215200700011 DATA MISC 2215200700012 MEV MEV 2215200700013 6.9630E+01 7.3000E+00 2215200700014 ENDDATA 3 0 2215200700015 ENDSUBENT 14 0 2215200799999 SUBENT 22152008 20090216 22072215200800001 BIB 4 7 2215200800002 REACTION (92-U-235(N,F),SEC,AKE,HF,MXW) Average kinetic energy 2215200800003 of post-neutron-emission heavy fragment. 2215200800004 MISC-COL (MISC) Standard deviaton. RMS width. 2215200800005 STATUS (TABLE) Data taken from main reference, Table 1 . 2215200800006 HISTORY (19900821C) S.W. 2215200800007 (19900917E) 2215200800008 (20090216A) SEC was added in SF5 of Reaction. 2215200800009 ENDBIB 7 0 2215200800010 NOCOMMON 0 0 2215200800011 DATA 2 1 2215200800012 DATA MISC 2215200800013 MEV MEV 2215200800014 6.9080E+01 7.2700E+00 2215200800015 ENDDATA 3 0 2215200800016 ENDSUBENT 15 0 2215200899999 SUBENT 22152009 20090216 22072215200900001 BIB 4 6 2215200900002 REACTION (92-U-235(N,F)MASS,PRE,FY,,MXW) Primary mass 2215200900003 distribution. 2215200900004 ERR-ANALYS (MASS-ERR-D) Digitizing error of MASS 2215200900005 (ERR-DIG) Digitizing error of DATA 2215200900006 STATUS (CURVE) Fig. 10 of main reference. 2215200900007 HISTORY (20090216C) M.M. 2215200900008 ENDBIB 6 0 2215200900009 COMMON 2 3 2215200900010 MASS-ERR-D ERR-DIG 2215200900011 NO-DIM PC/FIS 2215200900012 0.630E-01 0.562E-02 2215200900013 ENDCOMMON 3 0 2215200900014 DATA 2 64 2215200900015 MASS DATA 2215200900016 NO-DIM PC/FIS 2215200900017 79. 0.73882E-01 2215200900018 80. 0.13225 2215200900019 81. 0.19017 2215200900020 82. 0.27909 2215200900021 83. 0.42868 2215200900022 84. 0.65513 2215200900023 85. 0.98807 2215200900024 86. 1.3669 2215200900025 87. 1.7924 2215200900026 88. 2.4008 2215200900027 89. 3.0092 2215200900028 90. 4.0770 2215200900029 91. 5.0220 2215200900030 92. 5.7527 2215200900031 93. 5.9481 2215200900032 94. 5.9912 2215200900033 95. 6.4616 2215200900034 96. 6.5047 2215200900035 97. 6.3636 2215200900036 98. 6.0242 2215200900037 99. 5.7918 2215200900038 100. 5.4367 2215200900039 101. 5.5409 2215200900040 102. 5.3229 2215200900041 103. 4.8308 2215200900042 104. 3.5733 2215200900043 105. 2.4843 2215200900044 106. 1.6250 2215200900045 107. 0.94903 2215200900046 108. 0.44115 2215200900047 109. 0.19347 2215200900048 110. 0.83311E-01 2215200900049 126. 0.94062E-01 2215200900050 127. 0.21355 2215200900051 128. 0.45527 2215200900052 129. 0.97157 2215200900053 130. 1.6106 2215200900054 131. 2.4639 2215200900055 132. 3.5617 2215200900056 133. 4.8281 2215200900057 134. 5.3138 2215200900058 135. 5.5403 2215200900059 136. 5.4607 2215200900060 137. 5.7631 2215200900061 138. 6.0201 2215200900062 139. 6.3382 2215200900063 140. 6.4878 2215200900064 141. 6.4383 2215200900065 142. 5.9767 2215200900066 143. 5.9276 2215200900067 144. 5.7258 2215200900068 145. 5.0193 2215200900069 146. 4.0683 2215200900070 147. 3.0252 2215200900071 148. 2.4103 2215200900072 149. 1.7802 2215200900073 150. 1.3640 2215200900074 151. 0.97837 2215200900075 152. 0.65430 2215200900076 153. 0.42190 2215200900077 154. 0.25016 2215200900078 155. 0.17102 2215200900079 156. 0.12152 2215200900080 157. 0.72932E-01 2215200900081 ENDDATA 66 0 2215200900082 ENDSUBENT 81 0 2215200999999 SUBENT 22152010 20180829 22702215201000001 BIB 4 9 2215201000002 REACTION (92-U-235(N,F)MASS,PRE,KE,LF+HF,MXW) Total kinetic 2215201000003 energy dependence on fragment mass. 2215201000004 ERR-ANALYS (DATA-ERR) Error bar of Fig.11, when was possible to 2215201000005 digitize. In other cases - errors less then size of 2215201000006 data points. 2215201000007 STATUS (CURVE) Fig. 11 from Nucl.Inst Meth.A286(1990)220 2215201000008 HISTORY (20090216C) M.M. 2215201000009 (20180829A) SD: SF7=KE/CRL -> KE, SF8=LF/HF -> LF+HF 2215201000010 in REACTION code. 2215201000011 ENDBIB 9 0 2215201000012 COMMON 2 3 2215201000013 MASS-ERR-D ERR-DIG 2215201000014 NO-DIM MEV 2215201000015 0.1096 0.07739 2215201000016 ENDCOMMON 3 0 2215201000017 DATA 3 91 2215201000018 MASS DATA DATA-ERR 2215201000019 NO-DIM MEV MEV 2215201000020 74. 142.81 4.1225 2215201000021 75. 143.64 4.2259 2215201000022 76. 145.08 1.5463 2215201000023 77. 146.84 2.0612 2215201000024 78. 147.87 1.0306 2215201000025 79. 151.89 0.61874 2215201000026 80. 152.72 0.61838 2215201000027 81. 153.96 0.41226 2215201000028 82. 154.07 0.20613 2215201000029 83. 155.00 0.30919 2215201000030 84. 156.55 0.20613 2215201000031 85. 157.37 0.10307 2215201000032 86. 158.51 0.20612 2215201000033 87. 159.23 2215201000034 88. 160.27 2215201000035 89. 161.20 2215201000036 90. 162.64 2215201000037 91. 163.78 2215201000038 92. 164.81 2215201000039 93. 165.53 2215201000040 94. 166.16 2215201000041 95. 167.29 2215201000042 96. 168.63 2215201000043 97. 170.08 2215201000044 98. 171.22 2215201000045 99. 172.04 2215201000046 100. 173.49 2215201000047 101. 174.93 2215201000048 102. 176.79 2215201000049 103. 178.44 2215201000050 104. 179.17 2215201000051 105. 178.86 2215201000052 106. 179.07 2215201000053 107. 178.45 2215201000054 108. 176.91 0.20613 2215201000055 109. 174.75 0.20612 2215201000056 110. 171.66 0.41187 2215201000057 111. 169.60 0.72144 2215201000058 112. 168.26 1.0306 2215201000059 113. 166.31 1.7521 2215201000060 114. 167.44 2.1643 2215201000061 115. 169.41 2.9888 2215201000062 116. 168.58 3.1949 2215201000063 117. 166.01 6.4929 2215201000064 118. 159.52 2.3704 2215201000065 119. 156.22 1.3402 2215201000066 120. 159.63 2.2674 2215201000067 121. 166.12 6.4929 2215201000068 122. 168.50 3.2980 2215201000069 123. 169.43 2.8857 2215201000070 124. 167.37 2.2677 2215201000071 125. 166.34 1.6486 2215201000072 126. 168.20 1.1337 2215201000073 127. 169.64 0.61800 2215201000074 128. 171.60 0.41225 2215201000075 129. 174.70 0.20613 2215201000076 130. 176.86 0.30881 2215201000077 131. 178.52 2215201000078 132. 178.93 2215201000079 133. 178.83 2215201000080 134. 179.14 2215201000081 135. 178.42 2215201000082 136. 176.78 2215201000083 137. 174.92 2215201000084 138. 173.48 2215201000085 139. 172.04 2215201000086 140. 171.12 2215201000087 141. 169.99 2215201000088 142. 168.55 2215201000089 143. 167.21 2215201000090 144. 166.08 2215201000091 145. 165.46 2215201000092 146. 164.64 2215201000093 147. 163.72 2215201000094 148. 162.59 2215201000095 149. 161.15 2215201000096 150. 160.12 2215201000097 151. 159.09 2215201000098 152. 158.47 2215201000099 153. 157.24 2215201000100 154. 156.52 2215201000101 155. 154.98 0.20650 2215201000102 156. 153.95 0.20575 2215201000103 157. 153.85 0.51494 2215201000104 158. 152.61 0.72182 2215201000105 159. 151.79 0.72144 2215201000106 160. 147.78 1.1341 2215201000107 161. 146.75 1.9585 2215201000108 162. 145.00 1.6494 2215201000109 163. 143.56 4.1225 2215201000110 164. 142.74 4.1228 2215201000111 ENDDATA 93 0 2215201000112 ENDSUBENT 111 0 2215201099999 SUBENT 22152011 20090216 22072215201100001 BIB 3 4 2215201100002 REACTION (92-U-235(N,F),SEC,AKE,LF+HF,MXW) Average total 2215201100003 kinetic energy of both post-neutron-emission fragments.2215201100004 STATUS (TABLE) Data taken from main reference, Table 1 . 2215201100005 HISTORY (20090216C) M.M. 2215201100006 ENDBIB 4 0 2215201100007 NOCOMMON 0 0 2215201100008 DATA 1 1 2215201100009 DATA 2215201100010 MEV 2215201100011 168.44 2215201100012 ENDDATA 3 0 2215201100013 ENDSUBENT 12 0 2215201199999 ENDENTRY 11 0 2215299999999