ENTRY 21920 19870125 00002192000000001 SUBENT 21920001 19870125 00002192000100001 BIB 15 39 2192000100002 REFERENCE (J,PR/C,30,(1),72,8407) 2192000100003 (W,FISCHER,84) TEXT OF PR/C ARTICLE WITH EXTRA DATA 2192000100004 (P,INDC(AUS)-010/G,8404) 2192000100005 (J,PR/C,34,(2),460,8608) DATA FOR LEVEL DENSITIES 2192000100006 AND NUCLEAR TEMPERATURES FOR 26-FE-56 AND 28-NI-60. 2192000100007 TITLE -INVESTIGATION OF THE FE-56(N,A)CR-53 AND 2192000100008 NI-60(N,A)FE-57 REACTIONS 2192000100009 AUTHOR (R.FISCHER,G.TRAXLER,M.UHL,H.VONACH) 2192000100010 INSTITUTE (2AUSIRK) 2192000100011 FACILITY (CCW,2AUSIRK) 250KEV ACCELERATOR TO PRODUCE 2192000100012 14.1MEV NEUTRONS. 2192000100013 INC-SOURCE (D-T) 8.3 10**9N/S RESULTING IN NEUTRON FLUXES FROM 2192000100014 4.54.5 10**5 TO 2.0 10**5 N/CM**2*S 2192000100015 DETECTOR (TELES) MULTITELESCOPE ANGULAR RESOLUTION 13 DEGREES 2192000100016 (CSICR) ACCURACY .3 MEV 2192000100017 PART-DET (A) 2192000100018 METHOD (EDE) ENERGY AND ANGULAR DISTRIBUTIONS OF THE ALPHAS 2192000100019 PARTICLES FROM 22 TO 165 DEGREES 2192000100020 SAMPLE .TARGET OF IRON AND NICKEL MORE THAN 99 PER CENT IN 2192000100021 FE-56 AND NI-60.ROLLED TARGETS AVERAGE THICKNESS 2192000100022 .FE-56 2.15+-2 PER CENT 2192000100023 .NI-60 2.34+-2 PER CENT 2192000100024 TO REDUCE THE INHOMOGENEITIES,THE TARGET WAS ROTATED 2192000100025 BY 180 DEGREES IN THE MIDDLE OF EACH EXPERIMENT 2192000100026 CORRECTION .FOR THE ENERGY LOSS IN THE TARGETS ALL PARTICLES WERE 2192000100027 ASSUMED TO HAVE LOST AN ENERGY CORRESPONDING TO HALF 2192000100028 THE TARGET THICKNESS. 2192000100029 ANALYSIS (INTAD,INTED) 2192000100030 ADD-RES (ANGD) 2192000100031 (LD) 2192000100032 STATUS .DATA WERE TAKEN FROM PRIVATE COMMUNICATION 2192000100033 HISTORY (841018C) IF. 2192000100034 (850311E) 2192000100035 (850429U)HH. 2192000100036 (850502E) 2192000100037 (861105A) SUBENT 12-15 ADDED. NO. 2192000100038 (870519E) 2192000100039 (870125U) IF. 2192000100040 (880129E) 2192000100041 ENDBIB 39 0 2192000100042 NOCOMMON 0 0 2192000100043 ENDSUBENT 42 0 2192000199999 SUBENT 21920002 19870825 00002192000200001 BIB 4 14 2192000200002 REACTION (26-FE-56(N,X)2-HE-4,,DE) 2192000200003 ERR-ANALYS (ERR-T) TOTAL ERROR INCLUDES- 2192000200004 ERROR IN NEUTRON FLUX 3 PER CENT 2192000200005 ERROR IN EFFECTIVE TARGET THICKNESS 3.5 PER CENT 2192000200006 ERROR IN SOLID ANGLE TELESCOPE 1.7 PER CENT 2192000200007 DEAD TIME CORRECTION 1. PER CENT 2192000200008 ERROR FOR THE PARTICLE IDENTIFICATION 2. PER CENT 2192000200009 STATUS .DATA WERE TAKEN FROM TABLE 1. 2192000200010 HISTORY (841019C) IF. 2192000200011 (850311E) 2192000200012 (850429U)HH. 2192000200013 (850502E) 2192000200014 (870825U) IF. 2192000200015 (870827E) 2192000200016 ENDBIB 14 0 2192000200017 COMMON 1 3 2192000200018 EN 2192000200019 MEV 2192000200020 1.4100E+01 2192000200021 ENDCOMMON 3 0 2192000200022 DATA 4 10 2192000200023 E-MIN E-MAX DATA ERR-T 2192000200024 MEV MEV MB/MEV MB/MEV 2192000200025 5.0000E+00 6.0000E+00 1.6900E+00 2.0000E-01 2192000200026 6.0000E+00 7.0000E+00 4.3900E+00 2.8000E-01 2192000200027 7.0000E+00 8.0000E+00 8.6000E+00 4.3000E-01 2192000200028 8.0000E+00 9.0000E+00 1.0630E+01 5.1000E-01 2192000200029 9.0000E+00 1.0000E+01 7.4500E+00 3.7000E-01 2192000200030 1.0000E+01 1.1000E+01 4.6300E+00 2.5000E-01 2192000200031 1.1000E+01 1.2000E+01 2.9800E+00 1.8000E-01 2192000200032 1.2000E+01 1.3000E+01 2.0600E+00 1.3000E-01 2192000200033 1.3000E+01 1.4000E+01 7.5000E-01 8.0000E-02 2192000200034 1.4000E+01 1.5000E+01 2.3000E-01 6.0000E-02 2192000200035 ENDDATA 12 0 2192000200036 ENDSUBENT 35 0 2192000299999 SUBENT 21920003 19870825 00002192000300001 BIB 4 14 2192000300002 REACTION (26-FE-56(N,X)2-HE-4,,SIG) 2192000300003 ERR-ANALYS (ERR-T) TOTAL ERROR INCLUDES- 2192000300004 ERROR IN NEUTRON FLUX 3 PER CENT 2192000300005 ERROR IN EFFECTIVE TARGET THICKNESS 3.5 PER CENT 2192000300006 ERROR IN SOLID ANGLE TELESCOPE 1.7 PER CENT 2192000300007 DEAD TIME CORRECTION 1. PER CENT 2192000300008 ERROR FOR THE PARTICLE IDENTIFICATION 2. PER CENT 2192000300009 STATUS .DATA WERE TAKEN FROM TABLE 2. 2192000300010 HISTORY (841018C) IF. 2192000300011 (850311E) 2192000300012 (850429U)HH. 2192000300013 (850502E) 2192000300014 (870825U) IF. 2192000300015 (870827E) 2192000300016 ENDBIB 14 0 2192000300017 COMMON 1 3 2192000300018 EN 2192000300019 MEV 2192000300020 1.4100E+01 2192000300021 ENDCOMMON 3 0 2192000300022 DATA 2 1 2192000300023 DATA ERR-T 2192000300024 MB MB 2192000300025 4.4000E+01 2.0000E+00 2192000300026 ENDDATA 3 0 2192000300027 ENDSUBENT 26 0 2192000399999 SUBENT 21920004 19850311 00002192000400001 BIB 6 13 2192000400002 REACTION (24-CR-53(0,0),,SCO) SPIN CUT OFF PARAMETER 2192000400003 ANALYSIS .DETERMINED FROM THE ALPHA EMISSION SPECTRUM INTEGRATED2192000400004 OVER THE BACKWARD HEMISPHERE. 2192000400005 DEDUCED FROM THE LEVEL DENSITIES BY TWO WAYS. 2192000400006 FLAG (1.) COMPARISON WITH AVERAGE S WAWE SPACING 2192000400007 (2.)ANGULAR DISTRIBUTION OF EVAPORATED ALPHAS PARTICLES2192000400008 STATUS .DATA WERE TAKEN FROM TABLE 3. 2192000400009 HISTORY (841018C) IF. 2192000400010 (850311E) 2192000400011 ERR-ANALYS (+DATA-ERR) 2192000400012 (-DATA-ERR) 2192000400013 .NO EXPLANATION FOR THE UNSYMMETRIC ERROR 2192000400014 ON THE SPIN CUT OFF PARAMETER 2192000400015 ENDBIB 13 0 2192000400016 NOCOMMON 0 0 2192000400017 DATA 6 2 2192000400018 E-EXC-MAX E-EXC-MIN DATA +DATA-ERR -DATA-ERR FLAG 2192000400019 MEV MEV NO-DIM NO-DIM NO-DIM NO-DIM 2192000400020 7.9400E+00 4.1000E+00 6.0000E-01 6.0000E-01 1.0000E+002192000400021 7.8500E+00 3.8500E+00 4.0000E+00 1.6000E+00 6.0000E-01 2.0000E+002192000400022 ENDDATA 4 0 2192000400023 ENDSUBENT 22 0 2192000499999 SUBENT 21920005 19880125 00002192000500001 BIB 3 10 2192000500002 REACTION (24-CR-53(0,0),,TEM) NUCLEAR TEMPERATURE. 2192000500003 USING THE CONSTANT TEMPERATURE MODEL, 2192000500004 THE GIVEN NUCLEAR TEMPERATURE WAS CALCULATED FOR2192000500005 THE EXCITATION ENERGY REGION BELOW THE NEUTRON 2192000500006 BINDING ENERGY. 2192000500007 STATUS .DATA WERE TAKEN FROM PRIVATE COMMUNICATION. 2192000500008 HISTORY (841018C) IF. 2192000500009 (850311E) 2192000500010 (880125U) IF. 2192000500011 (880129E) 2192000500012 ENDBIB 10 0 2192000500013 NOCOMMON 0 0 2192000500014 DATA 2 1 2192000500015 DATA DATA-ERR 2192000500016 MEV MEV 2192000500017 1.2000E+00 3.0000E-02 2192000500018 ENDDATA 3 0 2192000500019 ENDSUBENT 18 0 2192000599999 SUBENT 21920006 19880125 00002192000600001 BIB 3 6 2192000600002 REACTION (26-FE-56(0,0),,TEM) NUCLEAR TEMPERATURE. 2192000600003 STATUS .DATA WERE TAKEN FROM PRIVATE COMMUNICATION. 2192000600004 HISTORY (841018C) IF. 2192000600005 (850311E) 2192000600006 (880125U) IF. 2192000600007 (880129E) 2192000600008 ENDBIB 6 0 2192000600009 NOCOMMON 0 0 2192000600010 DATA 4 1 2192000600011 E-EXC-MIN E-EXC-MAX DATA DATA-ERR 2192000600012 MEV MEV MEV MEV 2192000600013 4.0000E+00 1.1000E+01 4.4000E-01 7.0000E-02 2192000600014 ENDDATA 3 0 2192000600015 ENDSUBENT 14 0 2192000699999 SUBENT 21920007 19870825 00002192000700001 BIB 4 14 2192000700002 REACTION (28-NI-60(N,X)2-HE-4,,DE) 2192000700003 ERR-ANALYS (ERR-T) TOTAL ERROR INCLUDES- 2192000700004 ERROR IN NEUTRON FLUX 3 PER CENT 2192000700005 ERROR IN EFFECTIVE TARGET THICKNESS 3.5 PER CENT 2192000700006 ERROR IN SOLID ANGLE TELESCOPE 1.7 PER CENT 2192000700007 DEAD TIME CORRECTION 1. PER CENT 2192000700008 ERROR FOR THE PARTICLE IDENTIFICATION 2. PER CENT 2192000700009 STATUS .DATA WERE TAKEN FROM TABLE 1. 2192000700010 HISTORY (801018C) IF. 2192000700011 (850311E) 2192000700012 (850429U)HH. 2192000700013 (850502E) 2192000700014 (870825U) IF. 2192000700015 (870827E) 2192000700016 ENDBIB 14 0 2192000700017 COMMON 1 3 2192000700018 EN 2192000700019 MEV 2192000700020 1.4100E+01 2192000700021 ENDCOMMON 3 0 2192000700022 DATA 4 11 2192000700023 E-MIN E-MAX DATA ERR-T 2192000700024 MEV MEV MB/MEV MB/MEV 2192000700025 5.0000E+00 6.0000E+00 2.9800E+00 2.5000E-01 2192000700026 6.0000E+00 7.0000E+00 5.5900E+00 3.4000E-01 2192000700027 7.0000E+00 8.0000E+00 1.0910E+01 5.5000E-01 2192000700028 8.0000E+00 9.0000E+00 1.5230E+01 7.3000E-01 2192000700029 9.0000E+00 1.0000E+01 1.3540E+01 6.5000E-01 2192000700030 1.0000E+01 1.1000E+01 8.9600E+00 4.4000E-01 2192000700031 1.1000E+01 1.2000E+01 4.8700E+00 2.6000E-01 2192000700032 1.2000E+01 1.3000E+01 3.3500E+00 1.9000E-01 2192000700033 1.3000E+01 1.4000E+01 1.4600E+00 1.1000E-01 2192000700034 1.4000E+01 1.5000E+01 1.0400E+00 9.0000E-02 2192000700035 1.5000E+01 1.6000E+01 2.8000E-01 6.0000E-02 2192000700036 ENDDATA 13 0 2192000700037 ENDSUBENT 36 0 2192000799999 SUBENT 21920008 19870825 00002192000800001 BIB 4 14 2192000800002 REACTION (28-NI-60(N,X)2-HE-4,,SIG) 2192000800003 ERR-ANALYS (ERR-T) TOTAL ERROR INCLUDES- 2192000800004 ERROR IN NEUTRON FLUX 3 PER CENT 2192000800005 ERROR IN EFFECTIVE TARGET THICKNESS 3.5 PER CENT 2192000800006 ERROR IN SOLID ANGLE TELESCOPE 1.7 PER CENT 2192000800007 DEAD TIME CORRECTION 1. PER CENT 2192000800008 ERROR FOR THE PARTICLE IDENTIFICATION 2. PER CENT 2192000800009 STATUS .DATA WERE TAKEN FROM TABLE 2. 2192000800010 HISTORY (841018C) IF. 2192000800011 (850311E) 2192000800012 (850429U)HH. 2192000800013 (850502E) 2192000800014 (870825U) IF. 2192000800015 (870827E) 2192000800016 ENDBIB 14 0 2192000800017 COMMON 1 3 2192000800018 EN 2192000800019 MEV 2192000800020 1.4100E+01 2192000800021 ENDCOMMON 3 0 2192000800022 DATA 2 1 2192000800023 DATA ERR-T 2192000800024 MB MB 2192000800025 6.9600E+01 3.1000E+00 2192000800026 ENDDATA 3 0 2192000800027 ENDSUBENT 26 0 2192000899999 SUBENT 21920009 19880125 00002192000900001 BIB 6 16 2192000900002 REACTION (26-FE-57(0,0),,SCO) SPIN CUT OFF PARAMETER 2192000900003 ANALYSIS .DETERMINED FROM THE ALPHA EMISSION SPECTRUM INTEGRATED2192000900004 OVER THE BACKWARD HEMISPHERE. 2192000900005 DEDUCED FROM THE LEVEL DENSITIES BY TWO WAYS. 2192000900006 ERR-ANALYS (+DATA-ERR) 2192000900007 (-DATA-ERR) 2192000900008 .NO EXPLANATION FOR THE UNSYMMETRIC ERROR ON THE SPIN 2192000900009 CUT OFF PARAMETER 2192000900010 FLAG (1.) COMPARISON WITH AVERAGE S WAWE SPACING 2192000900011 (2.) ANGULAR DISTRIBUTION OF EVAPORATED ALPHAS 2192000900012 PARTICLES. 2192000900013 STATUS .DATA WERE TAKEN FROM TABLE 3. 2192000900014 HISTORY (841018C) IF. 2192000900015 (850311E) 2192000900016 (880125U) IF. 2192000900017 (880129E) 2192000900018 ENDBIB 16 0 2192000900019 NOCOMMON 0 0 2192000900020 DATA 6 2 2192000900021 E-EXC-MAX E-EXC-MIN DATA +DATA-ERR -DATA-ERR FLAG 2192000900022 MEV MEV NO-DIM NO-DIM NO-DIM NO-DIM 2192000900023 7.9400E+00 3.8000E+00 4.0000E-01 4.0000E-01 1.0000E+002192000900024 7.8500E+00 3.8500E+00 3.8000E+00 1.4000E+00 5.0000E-01 2.0000E+002192000900025 ENDDATA 4 0 2192000900026 ENDSUBENT 25 0 2192000999999 SUBENT 21920010 19880125 00002192001000001 BIB 3 10 2192001000002 REACTION (26-FE-57(0,0),,TEM) NUCLEAR TEMPERATURE. 2192001000003 USING THE CONSTANT TEMPERATURE MODEL, 2192001000004 THE GIVEN NUCLEAR TEMPERATURE WAS CALCULATED FOR2192001000005 THE EXCITATION ENERGY REGION BELOW THE NEUTRON 2192001000006 BINDING ENERGY. 2192001000007 STATUS .DATA WERE TAKEN FROM PRIVATE COMMUNICATION. 2192001000008 HISTORY (841018C) IF. 2192001000009 (850311E) 2192001000010 (880125U) IF. 2192001000011 (880129E) 2192001000012 ENDBIB 10 0 2192001000013 NOCOMMON 0 0 2192001000014 DATA 2 1 2192001000015 DATA DATA-ERR 2192001000016 MEV MEV 2192001000017 1.2200E+00 3.0000E-02 2192001000018 ENDDATA 3 0 2192001000019 ENDSUBENT 18 0 2192001099999 SUBENT 21920011 19880125 00002192001100001 BIB 3 6 2192001100002 REACTION (28-NI-60(0,0),,TEM) NUCLEAR TEMPERATURE. 2192001100003 STATUS .DATA WERE TAKEN FROM PRIVATE COMMUNICATION. 2192001100004 HISTORY (841018C) IF. 2192001100005 (850311E) 2192001100006 (880125U) IF. 2192001100007 (880129E) 2192001100008 ENDBIB 6 0 2192001100009 NOCOMMON 0 0 2192001100010 DATA 4 1 2192001100011 E-EXC-MIN E-EXC-MAX DATA DATA-ERR 2192001100012 MEV MEV MEV MEV 2192001100013 4.0000E+00 1.1000E+01 4.2000E-01 1.7000E-01 2192001100014 ENDDATA 3 0 2192001100015 ENDSUBENT 14 0 2192001199999 SUBENT 21920012 19870825 00002192001200001 BIB 4 8 2192001200002 REACTION (26-FE-56(0,0),,LDP) LEVEL DENSITY PARAMETER 2192001200003 ANALYSIS .DETERMINED FROM THE ALPHA EMISSION SPECTRUM 2192001200004 STATUS .DATA WERE TAKEN FROM TABLE 4 IN 2192001200005 PR/C,34,(2),460,8608 2192001200006 HISTORY (861105C) NO. 2192001200007 (870519E) 2192001200008 (870825U) IF. 2192001200009 (870827E) 2192001200010 ENDBIB 8 0 2192001200011 NOCOMMON 0 0 2192001200012 DATA 2 1 2192001200013 E-EXC DATA 2192001200014 MEV 1/MEV 2192001200015 1.1000E+01 3.0500E+03 2192001200016 ENDDATA 3 0 2192001200017 ENDSUBENT 16 0 2192001299999 SUBENT 21920013 19870519 00002192001300001 BIB 5 8 2192001300002 REACTION (26-FE-56(0,0),,TEM) 2192001300003 ANALYSIS .NUCLEAR TEMPERATURE DERIVED FROM EXPERIMENTAL 2192001300004 LEVEL DENSITY VALUES 2192001300005 STATUS .DATA WERE TAKEN FROM TABLE 4 IN 2192001300006 PR/C,34,(2),460,8608 2192001300007 HISTORY (861105C) NO. 2192001300008 (870519E) 2192001300009 ERR-ANALYS (ERR-T) 2192001300010 ENDBIB 8 0 2192001300011 NOCOMMON 0 0 2192001300012 DATA 4 1 2192001300013 E-EXC-MIN E-EXC-MAX DATA ERR-T 2192001300014 MEV MEV MEV MEV 2192001300015 3.0000E+00 1.1000E+01 1.4100E+00 7.0000E-02 2192001300016 ENDDATA 3 0 2192001300017 ENDSUBENT 16 0 2192001399999 SUBENT 21920014 19870825 00002192001400001 BIB 4 8 2192001400002 REACTION (28-NI-60(0,0),,LDP) LEVEL DENSITY PARAMETER 2192001400003 ANALYSIS .DETERMINED FROM THE ALPHA EMISSION SPECTRUM 2192001400004 STATUS .DATA WERE TAKEN FROM TABLE 4 IN 2192001400005 PR/C,34,(2),460,8608 2192001400006 HISTORY (861105C) NO. 2192001400007 (870519E) 2192001400008 (870825U) IF. 2192001400009 (870827E) 2192001400010 ENDBIB 8 0 2192001400011 NOCOMMON 0 0 2192001400012 DATA 2 1 2192001400013 E-EXC DATA 2192001400014 MEV 1/MEV 2192001400015 1.1000E+01 3.8500E+03 2192001400016 ENDDATA 3 0 2192001400017 ENDSUBENT 16 0 2192001499999 SUBENT 21920015 19870519 00002192001500001 BIB 5 8 2192001500002 REACTION (28-NI-60(0,0),,TEM) 2192001500003 ANALYSIS .NUCLEAR TEMPERATURE DERIVED FROM EXPERIMENTAL 2192001500004 LEVEL DENSITY VALUES 2192001500005 STATUS .DATA WERE TAKEN FROM TABLE 4 IN 2192001500006 PR/C,34,(2),460,8608 2192001500007 HISTORY (861105C) NO. 2192001500008 (870519E) 2192001500009 ERR-ANALYS (ERR-T) 2192001500010 ENDBIB 8 0 2192001500011 NOCOMMON 0 0 2192001500012 DATA 4 1 2192001500013 E-EXC-MIN E-EXC-MAX DATA ERR-T 2192001500014 MEV MEV MEV MEV 2192001500015 3.0000E+00 1.1000E+01 1.3900E+00 7.0000E-02 2192001500016 ENDDATA 3 0 2192001500017 ENDSUBENT 16 0 2192001599999 ENDENTRY 15 0 2192099999999