ENTRY D6138 20120320 D082D613800000001 SUBENT D6138001 20120320 D082D613800100001 BIB 12 21 D613800100002 TITLE Fission fragment folding angle distributions for the D613800100003 systems 11B+237Np, 12C+236U and 16O+232Th in the D613800100004 energy range 1.1 < E/VB < 2.1 D613800100005 AUTHOR (S.Kailas, D.M.Nadkarni, A.Chatterjee, A.Saxena, D613800100006 S.S.Kapoor, R.Vandenbosch, J.P.Lestone, J.F.Liang, D613800100007 D.J.Prindle, A.A.Sonzogni, J.D.Bierman) D613800100008 INSTITUTE (3INDTRM) Nuclear Physics Division D613800100009 (1USAWAU) Nuclear Physics Laboratory D613800100010 REFERENCE (J,PR/C,59,2580,1999) D613800100011 (J,PR/C,54,R977,1996) Anisotropy given in figures D613800100012 FACILITY (LINAC,1USAWAU) D613800100013 SAMPLE Metal oxide or fluoride of thickness 50 to 300 ug/cm2 D613800100014 deposited on 50 to 100 ug/cm2 carbon or nickel D613800100015 backings D613800100016 DETECTOR (PPAC,SIBAR) D613800100017 METHOD (TOF) D613800100018 ANALYSIS (INTAD) D613800100019 ERR-ANALYS (DATA-ERR) No information on source of uncertainties D613800100020 STATUS (TABLE) Table I of J,Phys.Rev.C 59(1999)2580 D613800100021 HISTORY (20110713C) Ranjita Mandal D613800100022 (20120320U) On. Finalized D613800100023 ENDBIB 21 0 D613800100024 NOCOMMON 0 0 D613800100025 ENDSUBENT 24 0 D613800199999 SUBENT D6138002 20120320 D082D613800200001 BIB 1 1 D613800200002 REACTION (90-TH-232(8-O-16,F),,SIG) D613800200003 ENDBIB 1 0 D613800200004 NOCOMMON 0 0 D613800200005 DATA 3 4 D613800200006 EN DATA DATA-ERR D613800200007 MEV MB MB D613800200008 144.8 1813. 108. D613800200009 125.0 1434. 84. D613800200010 110.0 1023. 61. D613800200011 100.0 658. 40. D613800200012 ENDDATA 6 0 D613800200013 ENDSUBENT 12 0 D613800299999 SUBENT D6138003 20120320 D082D613800300001 BIB 1 1 D613800300002 REACTION (92-U-236(6-C-12,F),,SIG) D613800300003 ENDBIB 1 0 D613800300004 NOCOMMON 0 0 D613800300005 DATA 3 5 D613800300006 EN DATA DATA-ERR D613800300007 MEV MB MB D613800300008 130.0 1948. 117. D613800300009 110.0 1800. 108. D613800300010 95.0 1497. 90. D613800300011 85.0 1039. 62. D613800300012 80.0 908. 63. D613800300013 ENDDATA 7 0 D613800300014 ENDSUBENT 13 0 D613800399999 SUBENT D6138004 20120320 D082D613800400001 BIB 1 1 D613800400002 REACTION (93-NP-237(5-B-11,F),,SIG) D613800400003 ENDBIB 1 0 D613800400004 NOCOMMON 0 0 D613800400005 DATA 3 3 D613800400006 EN DATA DATA-ERR D613800400007 MEV MB MB D613800400008 118.0 2023. 120. D613800400009 80.0 1388. 83. D613800400010 60.0 364. 25. D613800400011 ENDDATA 5 0 D613800400012 ENDSUBENT 11 0 D613800499999 SUBENT D6138005 20120320 D082D613800500001 BIB 1 5 D613800500002 REACTION 1(90-TH-232(8-O-16,F),,DA,FF,RSD) D613800500003 Anisotropy for Fusion-fission and transfer fission D613800500004 2(90-TH-232(8-O-16,F),,DA,FF,RSD/MSC) D613800500005 Anisotropy values for fusion-fission data alone after D613800500006 separating the transfer induced fission D613800500007 ENDBIB 5 0 D613800500008 COMMON 1 3 D613800500009 ANG D613800500010 ADEG D613800500011 180. D613800500012 ENDCOMMON 3 0 D613800500013 DATA 5 4 D613800500014 EN DATA 1DATA-ERR 1DATA 2DATA-ERR 2 D613800500015 MEV NO-DIM NO-DIM NO-DIM NO-DIM D613800500016 144.8 2.60 0.12 2.63 0.13 D613800500017 125.0 2.33 0.10 2.38 0.11 D613800500018 110.0 2.13 0.09 2.13 0.09 D613800500019 100.0 1.95 0.09 1.95 0.09 D613800500020 ENDDATA 6 0 D613800500021 ENDSUBENT 20 0 D613800599999 SUBENT D6138006 20120320 D082D613800600001 BIB 1 5 D613800600002 REACTION 1(92-U-236(6-C-12,F),,DA,FF,RSD) D613800600003 Anisotropy for Fusion-fission and transfer fission D613800600004 2(92-U-236(6-C-12,F),,DA,FF,RSD/MSC) D613800600005 Anisotropy values for fusion-fission data alone after D613800600006 separating the transfer induced fission D613800600007 ENDBIB 5 0 D613800600008 COMMON 1 3 D613800600009 ANG D613800600010 ADEG D613800600011 180. D613800600012 ENDCOMMON 3 0 D613800600013 DATA 5 5 D613800600014 EN DATA 1DATA-ERR 1DATA 2DATA-ERR 2 D613800600015 MEV NO-DIM NO-DIM NO-DIM NO-DIM D613800600016 130.0 2.25 0.10 2.36 0.12 D613800600017 110.0 2.17 0.09 2.34 0.14 D613800600018 95.0 2.05 0.09 2.08 0.10 D613800600019 85.0 1.78 0.09 1.78 0.09 D613800600020 80.0 1.68 0.10 1.68 0.10 D613800600021 ENDDATA 7 0 D613800600022 ENDSUBENT 21 0 D613800699999 SUBENT D6138007 20120320 D082D613800700001 BIB 1 5 D613800700002 REACTION 1(93-NP-237(5-B-11,F),,DA,FF,RSD) D613800700003 Anisotropy for Fusion-fission and transfer fission D613800700004 2(93-NP-237(5-B-11,F),,DA,FF,RSD/MSC) D613800700005 Anisotropy values for fusion-fission data alone after D613800700006 separating the transfer induced fission D613800700007 ENDBIB 5 0 D613800700008 COMMON 1 3 D613800700009 ANG D613800700010 ADEG D613800700011 180. D613800700012 ENDCOMMON 3 0 D613800700013 DATA 5 3 D613800700014 EN DATA 1DATA-ERR 1DATA 2DATA-ERR 2 D613800700015 MEV NO-DIM NO-DIM NO-DIM NO-DIM D613800700016 118.0 2.04 0.11 2.12 0.12 D613800700017 80.0 1.74 0.09 1.74 0.09 D613800700018 60.0 1.40 0.10 1.40 0.10 D613800700019 ENDDATA 5 0 D613800700020 ENDSUBENT 19 0 D613800799999 ENDENTRY 7 0 D613899999999