ENTRY 30458 20090420 31353045800000001 SUBENT 30458001 20090420 31353045800100001 BIB 13 44 3045800100002 INSTITUTE (3BULBLA) 3045800100003 (3DDRZFI) 1st author's address. 3045800100004 REFERENCE (J,RCA,23,(3),127,1976) in German. 3045800100005 AUTHOR (G.Pfrepper,C.Raitschev) 3045800100006 TITLE -Determination of the cross-sections of several (n,p)- 3045800100007 and (n,a)-reactions for fission neutrons.- 3045800100008 INC-SOURCE (REAC) n-flux at irradiation = 4 to 6.x10**12 n/sec/cm23045800100009 FACILITY (REAC,3BULBLA) Research reactor at Institut fuer 3045800100010 Kernforschung u.Kernenergetik, Bulgarian Academy 3045800100011 of Science, Sofia. 3045800100012 INC-SPECT The ratios of thermal and fast component in the neutron3045800100013 beam were determined to be, 3045800100014 ''5.08+-0.08'' and ''5.34+-0.13''at beam hole-4.using3045800100015 the reactions of P-31(n,g)P-32 and S-32(n,p)P-32, and 3045800100016 Na-23(n,g)Na-24.and Al-27(n,a)Na-24, 3045800100017 respectively, and 3045800100018 ''7.31+-0.12'',at pneumatic position, using the 3045800100019 reactions of P-31(n,g)P-32 and S-32(n,p)P-32. 3045800100020 METHOD (CHSEP,MOMIX) 3045800100021 (n,g) reaction leading to the same residual nuclide of3045800100022 (n,p) or (n,a) reaction was used for comparison. 3045800100023 After irradiation of the mixed sample, radio-chemical 3045800100024 separation was performed and the specific gamma peaks 3045800100025 from the residual nuclide were measured by Ge(Li). 3045800100026 DETECTOR (GELI) 18 cm3 Ge(Li) detector. 3045800100027 ANALYSIS The cross-section of (n,p) or (n,a) reaction, sig(S) 3045800100028 is deduced from the following equation. 3045800100029 Sig(S)=sig(t)*(f(t)/f(S))*(1/p)*(r/(r-1))*(1/r') , 3045800100030 where 3045800100031 .sig(t) = (n,g)cross-section for thermal neutron. 3045800100032 .f(t)/f(S) = flux ratio of thermal to fission neutron 3045800100033 .p = isotopic distribution coef. which is defined 3045800100034 as a ratio of amounts of the target(for threshold 3045800100035 reaction) and the standard(for (n,g)reaction) yield- 3045800100036 ing same activities of the daughter nuclide considered3045800100037 .r= cadmium ratio (n,g) reaction, 3045800100038 .r'=cadmium ratio of threshold((n,p)or (n,a)) reaction.3045800100039 STATUS (APRVD) Approved by Pfrepper, 79/01/05. 3045800100040 HISTORY (19781006C) KO. 3045800100041 (19790125U) KO.-'Aprvd' added- 3045800100042 (20090310A) SD:Updated to new date formats,lower case. 3045800100043 OS. MONITOR coding revised. 3045800100044 ERR-ANALYS (DATA-ERR) Standard deviation of the mean value from 3045800100045 several experimental runs. 3045800100046 ENDBIB 44 0 3045800100047 NOCOMMON 0 0 3045800100048 ENDSUBENT 47 0 3045800199999 SUBENT 30458002 20090420 31353045800200001 BIB 6 16 3045800200002 REACTION (14-SI-28(N,P)13-AL-28,,SIG,,FIS) 3045800200003 SAMPLE High purity silicon 70 to 100 mg, together with 0.4 to 3045800200004 0.8 mg aluminium as the standard sample. 3045800200005 DECAY-DATA (13-AL-28,,DG,1778.) 3045800200006 MONITOR ((MONIT1)13-AL-27(N,G)13-AL-28,,SIG,,MXW) 3045800200007 232 mb,r(Cd) = 95.5 3045800200008 ((MONIT2)15-P-31(N,G)15-P-32,,SIG,,MXW) 3045800200009 190 mb,r(Cd) = 68. 3045800200010 ((MONIT3)16-S-32(N,P)15-P-32,,SIG,,FIS) 3045800200011 69 mb,r(Cd) = .1. 3045800200012 MONIT-REF (,R.Sher+,R,IAEA-156,1,1967) 3045800200013 all from R.Sher,Tech.Rep.Ser.IAEA-156,p.1 (1974) 3045800200014 .P-31(n,g)P-32 and S-32(n,p)P-32, reactions were used 3045800200015 to determine the flux ratio of thermal and fission 3045800200016 neutrons 3045800200017 STATUS (TABLE) From Table 2 of Radiochimica Acta 23(1976)127. 3045800200018 ENDBIB 16 0 3045800200019 COMMON 3 3 3045800200020 MONIT1 MONIT2 MONIT3 3045800200021 MB MB MB 3045800200022 2.3200E+02 1.9000E+02 6.9000E+01 3045800200023 ENDCOMMON 3 0 3045800200024 DATA 3 1 3045800200025 EN-DUMMY DATA DATA-ERR 3045800200026 MEV MB MB 3045800200027 2.0000E+00 7.2000E+00 3.0000E-01 3045800200028 ENDDATA 3 0 3045800200029 ENDSUBENT 28 0 3045800299999 SUBENT 30458003 20090420 31353045800300001 BIB 6 16 3045800300002 REACTION (15-P-31(N,A)13-AL-28,,SIG,,FIS) 3045800300003 SAMPLE (NH(4))(2)-HPO(4), 200 to 300 mg, together with 0.4 to3045800300004 0.8 mg aluminium as the standard sample. 3045800300005 DECAY-DATA (13-AL-28,,DG,1778.) 3045800300006 MONITOR ((MONIT1)13-AL-27(N,G)13-AL-28,,SIG,,MXW) 3045800300007 232 mb,r(Cd) = 95.5 3045800300008 ((MONIT2)15-P-31(N,G)15-P-32,,SIG,,MXW) 3045800300009 190 mb,r(Cd) = 68. 3045800300010 ((MONIT3)16-S-32(N,P)15-P-32,,SIG,,FIS) 3045800300011 69 mb,r(Cd) = .1. 3045800300012 MONIT-REF (,R.Sher+,R,IAEA-156,1,1967) 3045800300013 all from R.Sher,Tech.Rep.Ser.IAEA-156,p.1 (1974) 3045800300014 .P-31(n,g)P-32 and S-32(n,p)P-32 reactions were used 3045800300015 to determine the flux ratio of thermal and fission 3045800300016 neutrons. 3045800300017 STATUS (TABLE) From Table 3 of Radiochimica Acta 23(1976)127. 3045800300018 ENDBIB 16 0 3045800300019 COMMON 3 3 3045800300020 MONIT1 MONIT2 MONIT3 3045800300021 MB MB MB 3045800300022 2.3200E+02 1.9000E+02 6.9000E+01 3045800300023 ENDCOMMON 3 0 3045800300024 DATA 3 1 3045800300025 EN-DUMMY DATA DATA-ERR 3045800300026 MEV MB MB 3045800300027 2.0000E+00 2.7300E+00 7.0000E-02 3045800300028 ENDDATA 3 0 3045800300029 ENDSUBENT 28 0 3045800399999 SUBENT 30458004 20090420 31353045800400001 BIB 6 16 3045800400002 REACTION (14-SI-30(N,A)12-MG-27,,SIG,,FIS) 3045800400003 SAMPLE High purity silicon 70 to 100 mg, together with 0.5 to 3045800400004 0.6 mg magnesium as the standard sample. 3045800400005 DECAY-DATA (12-MG-27,,DG,844.,,DG,1014.) 3045800400006 MONITOR ((MONIT1)12-MG-26(N,G)12-MG-27,,SIG,,MXW) 3045800400007 38 mb,r(Cd) = 91.2 3045800400008 ((MONIT2)15-P-31(N,G)15-P-32,,SIG,,MXW) 3045800400009 190 mb,r(Cd) = 68. 3045800400010 ((MONIT3)16-S-32(N,P)15-P-32,,SIG,,FIS) 3045800400011 69 mb,r(Cd) = 1. 3045800400012 MONIT-REF (,R.Sher+,R,IAEA-156,1,1967) 3045800400013 all from r.Sher,tech.Rep.Ser.IAEA-156,p.1 (1974) 3045800400014 .P-31(n,g)P-32 and S-32(n,p)P-32 reactions were used 3045800400015 to determine the flux ratio of thermal and fission 3045800400016 neutrons. 3045800400017 STATUS (TABLE) From Table 4 of Radiochimica Acta 23(1976)127. 3045800400018 ENDBIB 16 0 3045800400019 COMMON 3 3 3045800400020 MONIT1 MONIT2 MONIT3 3045800400021 MB MB MB 3045800400022 3.8000E+01 1.9000E+02 6.9000E+01 3045800400023 ENDCOMMON 3 0 3045800400024 DATA 3 1 3045800400025 EN-DUMMY DATA DATA-ERR 3045800400026 MEV MB MB 3045800400027 2.0000E+00 1.3600E-01 1.1000E-02 3045800400028 ENDDATA 3 0 3045800400029 ENDSUBENT 28 0 3045800499999 SUBENT 30458005 20090420 31353045800500001 BIB 6 17 3045800500002 REACTION (30-ZN-66(N,P)29-CU-66,,SIG,,FIS) 3045800500003 SAMPLE Zn-SO(4)-7H(2)-O or Zn-(NO(3)(2)) 500 to 700 mg , 3045800500004 together with 5 to 10 mg metallic copper as the 3045800500005 standard sample. 3045800500006 DECAY-DATA (29-CU-66,5.1MIN,DG,1039.) 3045800500007 MONITOR ((MONIT1)29-CU-65(N,G)29-CU-66,,SIG,,MXW) 3045800500008 2200 mb,r(Cd) = 66.4 3045800500009 ((MONIT2)15-P-31(N,G)15-P-32,,SIG,,MXW) 3045800500010 190 mb,r(Cd) = 68. 3045800500011 ((MONIT3)16-S-32(N,P)15-P-32,,SIG,,FIS) 3045800500012 69 mb,r(Cd) = 1. 3045800500013 MONIT-REF (,R.Sher+,R,IAEA-156,1,1967) 3045800500014 all from R.Sher,Tech.Rep.Ser.IAEA-156,p.1 (1974) 3045800500015 .P-31(n,g)P-32 and S-32(n,p)P-32 reactions were used 3045800500016 to determine the flux ratio of thermal and fission 3045800500017 neutrons. 3045800500018 STATUS (TABLE) From Table 5 of Rradiochimica Acta 23(1976)127.3045800500019 ENDBIB 17 0 3045800500020 COMMON 3 3 3045800500021 MONIT1 MONIT2 MONIT3 3045800500022 MB MB MB 3045800500023 2.2000E+03 1.9000E+02 6.9000E+01 3045800500024 ENDCOMMON 3 0 3045800500025 DATA 3 1 3045800500026 EN-DUMMY DATA DATA-ERR 3045800500027 MEV MB MB 3045800500028 2.0000E+00 9.6000E-01 4.0000E-02 3045800500029 ENDDATA 3 0 3045800500030 ENDSUBENT 29 0 3045800599999 SUBENT 30458006 20090420 31353045800600001 BIB 6 24 3045800600002 REACTION 1(30-ZN-64(N,P)29-CU-64,,SIG,,FIS) 3045800600003 at the pneumatic position. 3045800600004 2(30-ZN-64(N,P)29-CU-64,,SIG,,FIS) 3045800600005 At the beam hole no.4. 3045800600006 SAMPLE Zn-SO(4)-7H(2)-O or Zn-(NO(3)(2) 200 to 300 mg, 3045800600007 together with 5 to 10 mg metallic copper as the 3045800600008 standard sample. 3045800600009 DECAY-DATA (29-CU-64,12.9HR,AR) 3045800600010 MONITOR ((MONIT1)29-CU-63(N,G)29-CU-64,,SIG,,MXW) 3045800600011 4400 mb,r(Cd) = 35.2 3045800600012 1((MONIT2)15-P-31(N,G)15-P-32,,SIG,,MXW) 3045800600013 190 mb,r(Cd) = 68. 3045800600014 ((MONIT3)16-S-32(N,P)15-P-32,,SIG,,FIS) 3045800600015 69 mb,r(Cd) = 1. 3045800600016 2((MONIT4)11-NA-23(N,G)11-NA-24,,SIG,,MXW) 3045800600017 528 mb,r(Cd) = 62. 3045800600018 ((MONIT5)13-AL-27(N,A)11-NA-24,,SIG,,FIS) 3045800600019 0.725mb,r(Cd) = 1. 3045800600020 MONIT-REF (,R.Sher+,R,IAEA-156,1,1974) 3045800600021 All monitor values are taken from R.Sher,IAEA-156(1974)3045800600022 .P-31(n,g),S-32(n,p), Na 23(n,g),Al-27(n,a) reactions 3045800600023 were used to determine the flux ratio of thermal and 3045800600024 fission neutrons. 3045800600025 STATUS (TABLE) From Table 6 of Radiochimica Acta,23(1976)127. 3045800600026 ENDBIB 24 0 3045800600027 COMMON 1 3 3045800600028 MONIT1 3045800600029 MB 3045800600030 4.4000E+03 3045800600031 ENDCOMMON 3 0 3045800600032 DATA 9 1 3045800600033 EN-DUMMY DATA 1DATA-ERR 1MONIT2 1MONIT3 1DATA 23045800600034 DATA-ERR 2MONIT4 2MONIT5 2 3045800600035 MEV MB MB MB MB MB 3045800600036 MB MB MB 3045800600037 2.0000E+00 2.7400E+01 8.0000E-01 1.9000E+02 6.9000E+01 2.8500E+013045800600038 1.7000E+00 5.2800E+02 7.2500E-01 3045800600039 ENDDATA 6 0 3045800600040 ENDSUBENT 39 0 3045800699999 ENDENTRY 6 0 3045899999999