ENTRY C2477 20200220 C191C247700000001 SUBENT C2477001 20200220 C191C247700100001 BIB 10 22 C247700100002 TITLE The 65 MeV helium ion-induced fission of 194Pt, 195Pt C247700100003 and 196Pt C247700100004 AUTHOR (E.F.Neuzil,K.Apt,W.Hensley,D.Assink) C247700100005 REFERENCE (J,JIN,31,1575,1969) C247700100006 #doi:10.1016/0022-1902(69)80372-6 C247700100007 REL-REF The radiochemical techniques used for the C247700100008 purification of fission products: C247700100009 (M,C2473001,E.F.Neuzil,J,JIN,27,3,1965) C247700100010 (M,C2431001,E.F.Neuzil+,J,JIN,27,1463,1965) C247700100011 INSTITUTE (1USAWWS) C247700100012 FACILITY (CYCLO,1USABRK) The 88 in. cyclotron at the Lawrence C247700100013 Radiation Laboratory in Berkeley, California. C247700100014 SAMPLE Targets of enriched isotopes of 194Pt, 195Pt, and C247700100015 l96Pt, in the form of thin (~6 mg/cm2) foils. C247700100016 METHOD (CHSEP) Targets of enriched isotopes were prepared C247700100017 in the usual manner and bombarded with 65 MeV helium C247700100018 ions in Berkeley, California. The targets were then C247700100019 flown to our laboratories in Bellingham where the C247700100020 fission fragments were separated and purified by C247700100021 standard radiochemical techniques. C247700100022 ERR-ANALYS (DATA-ERR,,20.) Probable error of +/-20% or less. C247700100023 HISTORY (20200220C) BP C247700100024 ENDBIB 22 0 C247700100025 COMMON 1 3 C247700100026 EN C247700100027 MEV C247700100028 65.0 C247700100029 ENDCOMMON 3 0 C247700100030 ENDSUBENT 29 0 C247700199999 SUBENT C2477002 20200220 C191C247700200001 BIB 2 2 C247700200002 REACTION (78-PT-194(A,F)ELEM/MASS,,SIG) C247700200003 STATUS (TABLE) Table 1, page 1576. C247700200004 ENDBIB 2 0 C247700200005 NOCOMMON 0 0 C247700200006 DATA 3 9 C247700200007 ELEMENT MASS DATA C247700200008 NO-DIM NO-DIM MICRO-B C247700200009 38.0 91.0 170.0 C247700200010 38.0 92.0 200.0 C247700200011 39.0 93.0 220.0 C247700200012 40.0 97.0 233.0 C247700200013 42.0 99.0 270.0 C247700200014 46.0 109.0 170.0 C247700200015 46.0 112.0 140.0 C247700200016 47.0 111.0 105.0 C247700200017 47.0 113.0 47.0 C247700200018 ENDDATA 11 0 C247700200019 ENDSUBENT 18 0 C247700299999 SUBENT C2477003 20200220 C191C247700300001 BIB 2 2 C247700300002 REACTION (78-PT-195(A,F)ELEM/MASS,,SIG) C247700300003 STATUS (TABLE) Table 1, page 1576. C247700300004 ENDBIB 2 0 C247700300005 NOCOMMON 0 0 C247700300006 DATA 3 9 C247700300007 ELEMENT MASS DATA C247700300008 NO-DIM NO-DIM MICRO-B C247700300009 38.0 91.0 91.0 C247700300010 38.0 92.0 90.0 C247700300011 39.0 93.0 109.0 C247700300012 40.0 97.0 126.0 C247700300013 42.0 99.0 131.0 C247700300014 46.0 109.0 42.5 C247700300015 46.0 112.0 45.3 C247700300016 47.0 111.0 40.2 C247700300017 47.0 113.0 20.0 C247700300018 ENDDATA 11 0 C247700300019 ENDSUBENT 18 0 C247700399999 SUBENT C2477004 20200220 C191C247700400001 BIB 2 2 C247700400002 REACTION (78-PT-196(A,F)ELEM/MASS,,SIG) C247700400003 STATUS (TABLE) Table 1, page 1576. C247700400004 ENDBIB 2 0 C247700400005 NOCOMMON 0 0 C247700400006 DATA 3 9 C247700400007 ELEMENT MASS DATA C247700400008 NO-DIM NO-DIM MICRO-B C247700400009 38.0 91.0 60.2 C247700400010 38.0 92.0 70.5 C247700400011 39.0 93.0 81.0 C247700400012 40.0 97.0 83.5 C247700400013 42.0 99.0 95.0 C247700400014 46.0 109.0 59.5 C247700400015 46.0 112.0 49.5 C247700400016 47.0 111.0 37.4 C247700400017 47.0 113.0 16.6 C247700400018 ENDDATA 11 0 C247700400019 ENDSUBENT 18 0 C247700499999 SUBENT C2477005 20200220 C191C247700500001 BIB 3 6 C247700500002 REACTION (78-PT-194(A,F),,SIG,,,DERIV) C247700500003 ANALYSIS The total fission cross section was obtained by C247700500004 summing the individual resolved fission fragment C247700500005 cross sections. C247700500006 STATUS (DEP,C2477002) C247700500007 (TABLE) page 1578. C247700500008 ENDBIB 6 0 C247700500009 NOCOMMON 0 0 C247700500010 DATA 1 1 C247700500011 DATA C247700500012 MB C247700500013 6.20 C247700500014 ENDDATA 3 0 C247700500015 ENDSUBENT 14 0 C247700599999 SUBENT C2477006 20200220 C191C247700600001 BIB 3 6 C247700600002 REACTION (78-PT-195(A,F),,SIG,,,DERIV) C247700600003 ANALYSIS The total fission cross section was obtained by C247700600004 summing the individual resolved fission fragment C247700600005 cross sections. C247700600006 STATUS (DEP,C2477003) C247700600007 (TABLE) page 1578. C247700600008 ENDBIB 6 0 C247700600009 NOCOMMON 0 0 C247700600010 DATA 1 1 C247700600011 DATA C247700600012 MB C247700600013 3.14 C247700600014 ENDDATA 3 0 C247700600015 ENDSUBENT 14 0 C247700699999 SUBENT C2477007 20200220 C191C247700700001 BIB 3 6 C247700700002 REACTION (78-PT-196(A,F),,SIG,,,DERIV) C247700700003 ANALYSIS The total fission cross section was obtained by C247700700004 summing the individual resolved fission fragment C247700700005 cross sections. C247700700006 STATUS (DEP,C2477004) C247700700007 (TABLE) page 1578. C247700700008 ENDBIB 6 0 C247700700009 NOCOMMON 0 0 C247700700010 DATA 1 1 C247700700011 DATA C247700700012 MB C247700700013 2.24 C247700700014 ENDDATA 3 0 C247700700015 ENDSUBENT 14 0 C247700799999 ENDENTRY 7 0 C247799999999