ENTRY 20049 20120708 22322004900000001 SUBENT 20049001 20120708 22322004900100001 BIB 12 36 2004900100002 INSTITUTE (2SWDAE ) 2004900100003 REFERENCE (J,JNE/AB,14,53,196101) 2004900100004 AUTHOR (R.Dahlberg,K.Jirlow,E.Johansson) 2004900100005 TITLE Measurements of some resonance activation integrals 2004900100006 FACILITY (REAC,2SWDAE ) Heavy water reactor R1. 2004900100007 (CHOPF) fast chopper 2004900100008 REL-REF (I,20048001,K.Jirlow+,J,JNE/A,11,101,1960) - 2004900100009 The neutron source description 2004900100010 (M,,E.Johansson+,J,AF,18,513,1960) - The neutron 2004900100011 spectrum in the beam was accurately known from 2004900100012 measurements with a fast chopper, as described 2004900100013 by Johansson et al. (1960). 2004900100014 DETECTOR (BF3) 2004900100015 METHOD (ACTIV) Activation 2004900100016 Cadmium ratio measurements in a neutron beam2004900100017 .Comparison was made with the cadmium ratio of 2004900100018 a 1/v detector, (a thin B-F(3) counter). 2004900100019 .The neutron spectra were measured with a chopper 2004900100020 CORRECTION .For deviation of the flux from 1/E dependence 2004900100021 .For scattering and self-absorption of neutrons in the 2004900100022 foils. Multiple scattering as well as energy changes 2004900100023 in the collisions have been taken into account. 2004900100024 ERR-ANALYS (DATA-ERR) .The uncertainties caused by incomplete 2004900100025 knowledge of resonance parameters and by effect of 2004900100026 Doppler broadening have been included in the final 2004900100027 values for the resonance integrals. 2004900100028 STATUS (TABLE) Data from Table 1 of JNE/AB,14,53,1961 2004900100029 HISTORY (19700502T) From NEUDADA file 2004900100030 (19710908E) 2004900100031 (19860311A)N.Ch 2004900100032 (19860416E) 2004900100033 (20120708A) SD: Updated to new date formats,lower case.2004900100034 Corrections according last EXFOR rules and Dict. 2004900100035 BIB update. Energy units in Subent 7 corrected. 2004900100036 SF8=RV -> RNV in REACTION codes in Subents 2-6,8. 2004900100037 Subent 9, 10 were added. 2004900100038 ENDBIB 36 0 2004900100039 NOCOMMON 0 0 2004900100040 ENDSUBENT 39 0 2004900199999 SUBENT 20049002 20120708 22322004900200001 BIB 6 14 2004900200002 REACTION (11-NA-23(N,G)11-NA-24,,RI,,RNV) 2004900200003 .The lower limit of the resonance integral has been 2004900200004 fixed at 0.5 eV and the 1/v part is not included. 2004900200005 INC-SOURCE (REAC) Reactor 2004900200006 SAMPLE Foil of 30. x 10**(-4) cm thick. 2004900200007 MONITOR (11-NA-23(N,G)11-NA-24,,SIG) 2004900200008 sigma(0.0253) = 0.520+-0.010 b. BNL-325 2004900200009 MONIT-REF (,D.J.Hughes+,R,BNL-325,1958) - D.J.Hughes,R.B.Schwartz2004900200010 Neutron Cross Sections, 2nd edn., U.S. Atomic Energy 2004900200011 Commission, BNL-325. 2004900200012 (,D.J.Hughes+,R,BNL-325,(S1),1960) - D.J.Hughes et al.2004900200013 Neutron Cross-Sections, 2nd edn., Suppl. No. 1. 2004900200014 U.S. Atomic Energy Commission, BNL-325. 2004900200015 HISTORY (20120708A) SD: SF8=RV -> RNV in REACTION code. 2004900200016 ENDBIB 14 0 2004900200017 COMMON 3 3 2004900200018 EN-NRM MONIT MONIT-ERR 2004900200019 EV B B 2004900200020 0.0253 0.520 0.010 2004900200021 ENDCOMMON 3 0 2004900200022 DATA 3 1 2004900200023 EN-MIN DATA DATA-ERR 2004900200024 KEV B B 2004900200025 5.0000E-04 7.0000E-02 1.0000E-02 2004900200026 ENDDATA 3 0 2004900200027 ENDSUBENT 26 0 2004900299999 SUBENT 20049003 20120708 22322004900300001 BIB 5 13 2004900300002 REACTION (25-MN-55(N,G)25-MN-56,,RI,,RNV) 2004900300003 .The lower limit of the resonance integral has been 2004900300004 fixed at 0.5 eV and the 1/v part is not included. 2004900300005 INC-SOURCE (REAC) Reactor 2004900300006 MONITOR (25-MN-55(N,G)25-MN-56,,SIG) 2004900300007 sigma(0.0253) = 13.3+-0.2 barn, BNL-325 2004900300008 MONIT-REF (,D.J.Hughes+,R,BNL-325,1958) - D.J.Hughes,R.B.Schwartz2004900300009 Neutron Cross Sections, 2nd edn., U.S. Atomic Energy 2004900300010 Commission, BNL-325. 2004900300011 (,D.J.Hughes+,R,BNL-325,(S1),1960) - D.J.Hughes et al.2004900300012 Neutron Cross-Sections, 2nd edn., Suppl. No. 1. 2004900300013 U.S. Atomic Energy Commission, BNL-325. 2004900300014 HISTORY (20120708A) SD: SF8=RV -> RNV in REACTION code. 2004900300015 ENDBIB 13 0 2004900300016 COMMON 3 3 2004900300017 EN-NRM MONIT MONIT-ERR 2004900300018 EV B B 2004900300019 0.0253 13.3 0.2 2004900300020 ENDCOMMON 3 0 2004900300021 DATA 3 1 2004900300022 EN-MIN DATA DATA-ERR 2004900300023 KEV B B 2004900300024 5.0000E-04 8.1500E+00 6.0000E-01 2004900300025 ENDDATA 3 0 2004900300026 ENDSUBENT 25 0 2004900399999 SUBENT 20049004 20120708 22322004900400001 BIB 7 25 2004900400002 REACTION (27-CO-59(N,G)27-CO-60,,RI,,RV) 2004900400003 .The lower limit of the resonance integral has been 2004900400004 fixed at 0.5 eV and the 1/v part is not included. 2004900400005 INC-SOURCE (REAC) Reactor 2004900400006 MONITOR (27-CO-59(N,G)27-CO-60,,SIG) 2004900400007 sigma(0.0253) = 38.0+-0.7 barn, BNL-325 2004900400008 MONIT-REF (,D.J.Hughes+,R,BNL-325,1958) - D.J.Hughes,R.B.Schwartz2004900400009 Neutron Cross Sections, 2nd edn., U.S. Atomic Energy 2004900400010 Commission, BNL-325. 2004900400011 (,D.J.Hughes+,R,BNL-325,(S1),1960) - D.J.Hughes et al.2004900400012 Neutron Cross-Sections, 2nd edn., Suppl. No. 1. 2004900400013 U.S. Atomic Energy Commission, BNL-325. 2004900400014 DECAY-DATA (27-CO-60-M,10.4MIN) 2004900400015 COMMENT .The measurements were made on the isomer cobalt-60-m 2004900400016 whose half-life is 10.4 min. 2004900400017 .In the evaluation was assumed that the cross-section 2004900400018 ratios for the production of the 10.4 min and 5.2 year2004900400019 states are the same for thermal and resonance neutrons2004900400020 and thus a total RI of 55.2+-4.5 barns was obtained. 2004900400021 .If one includes the 1/v part one gets 72.3+-5.0 barns.2004900400022 This value compares well with the result 75+-5 barns 2004900400023 by Johnston et al., J.Nucl.Energy, 11(1960)95 and the 2004900400024 73+-5 barns by Eastwood et al., Chalk river report 2004900400025 CI-207, unpublished. 2004900400026 HISTORY (20120708A) SD: SF8=RV -> RNV in REACTION code. 2004900400027 ENDBIB 25 0 2004900400028 COMMON 3 3 2004900400029 EN-NRM MONIT MONIT-ERR 2004900400030 EV B B 2004900400031 0.0253 38.0 0.7 2004900400032 ENDCOMMON 3 0 2004900400033 DATA 3 1 2004900400034 EN-MIN DATA DATA-ERR 2004900400035 KEV B B 2004900400036 5.0000E-04 5.5200E+01 4.5000E+00 2004900400037 ENDDATA 3 0 2004900400038 ENDSUBENT 37 0 2004900499999 SUBENT 20049005 20120708 22322004900500001 BIB 5 14 2004900500002 REACTION (29-CU-63(N,G)29-CU-64,,RI,,RNV) 2004900500003 .The lower limit of the resonance integral has been 2004900500004 fixed at 0.5 eV and the 1/v part is not included. 2004900500005 INC-SOURCE (REAC) Reactor 2004900500006 MONITOR (29-CU-63(N,G)29-CU-64,,SIG) 2004900500007 sigma(0.0253) = 4.50 +- 0.15 barn, 2004900500008 from BNL-325 2004900500009 MONIT-REF (,D.J.Hughes+,R,BNL-325,1958) - D.J.Hughes,R.B.Schwartz2004900500010 Neutron Cross Sections, 2nd edn., U.S. Atomic Energy 2004900500011 Commission, BNL-325. 2004900500012 (,D.J.Hughes+,R,BNL-325,(S1),1960) - D.J.Hughes et al.2004900500013 Neutron Cross-Sections, 2nd edn., Suppl. No. 1. 2004900500014 U.S. Atomic Energy Commission, BNL-325. 2004900500015 HISTORY (20120708A) SD: SF8=RV -> RNV in REACTION code. 2004900500016 ENDBIB 14 0 2004900500017 COMMON 3 3 2004900500018 EN-NRM MONIT MONIT-ERR 2004900500019 EV B B 2004900500020 0.0253 4.50 0.15 2004900500021 ENDCOMMON 3 0 2004900500022 DATA 3 1 2004900500023 EN-MIN DATA DATA-ERR 2004900500024 KEV B B 2004900500025 5.0000E-04 3.0900E+00 1.5000E-01 2004900500026 ENDDATA 3 0 2004900500027 ENDSUBENT 26 0 2004900599999 SUBENT 20049006 20120708 22322004900600001 BIB 5 14 2004900600002 REACTION (29-CU-65(N,G)29-CU-66,,RI,,RNV) 2004900600003 .The lower limit of the resonance integral has been 2004900600004 fixed at 0.5 eV and the 1/v part is not included. 2004900600005 INC-SOURCE (REAC) Reactor 2004900600006 MONITOR (29-CU-65(N,G)29-CU-66,,SIG) 2004900600007 sigma(0.0253) = 2.0 +- 0.3 barns 2004900600008 from BNL-325 2004900600009 MONIT-REF (,D.J.Hughes+,R,BNL-325,1958) - D.J.Hughes,R.B.Schwartz2004900600010 Neutron Cross Sections, 2nd edn., U.S. Atomic Energy 2004900600011 Commission, BNL-325. 2004900600012 (,D.J.Hughes+,R,BNL-325,(S1),1960) - D.J.Hughes et al.2004900600013 Neutron Cross-Sections, 2nd edn., Suppl. No. 1. 2004900600014 U.S. Atomic Energy Commission, BNL-325. 2004900600015 HISTORY (20120708A) SD: SF8=RV -> RNV in REACTION code. 2004900600016 ENDBIB 14 0 2004900600017 COMMON 3 3 2004900600018 EN-NRM MONIT MONIT-ERR 2004900600019 EV B B 2004900600020 0.0253 2.0 0.3 2004900600021 ENDCOMMON 3 0 2004900600022 DATA 3 1 2004900600023 EN-MIN DATA DATA-ERR 2004900600024 KEV B B 2004900600025 5.0000E-04 1.3800E+00 2.3000E-01 2004900600026 ENDDATA 3 0 2004900600027 ENDSUBENT 26 0 2004900699999 SUBENT 20049007 20120708 22322004900700001 BIB 5 10 2004900700002 REACTION (42-MO-98(N,G)42-MO-99,,SIG,,MXW) 2004900700003 INC-SOURCE (THCOL) Thermal column of R1 reactor. 2004900700004 MONITOR (79-AU-197(N,G)79-AU-198,,SIG) 2004900700005 COMMENT .The thermal cross section given in BNL-325 appeared 2004900700006 too high, so it was determined in a separate measure- 2004900700007 ment. The cross section obtained is only about one 2004900700008 third of that given in BNL-325 2004900700009 HISTORY (19710708A) correction made in comments 2004900700010 (19710908E) 2004900700011 (20120708A) SD: Energy units were corrected. 2004900700012 ENDBIB 10 0 2004900700013 NOCOMMON 0 0 2004900700014 DATA 3 1 2004900700015 EN-DUMMY DATA DATA-ERR 2004900700016 EV B B 2004900700017 0.0253 1.8000E-01 2.0000E-02 2004900700018 ENDDATA 3 0 2004900700019 ENDSUBENT 18 0 2004900799999 SUBENT 20049008 20120708 22322004900800001 BIB 6 16 2004900800002 REACTION (42-MO-98(N,G)42-MO-99,,RI,,RNV) 2004900800003 .the lower limit of the resonance integral has been 2004900800004 fixed at 0.5 eV and the 1/v part is not included. 2004900800005 INC-SOURCE (REAC) Reactor 2004900800006 MONITOR (42-MO-98(N,G)42-MO-99,,SIG) 2004900800007 sigma(0.0253) = 0.18+-0.02 2004900800008 COMMENT .The thermal cross section given in BNL-325 appeared 2004900800009 too high, so it was determined in a separate measure- 2004900800010 ment. The cross section obtained is only about one 2004900800011 third of that given in BNL-325. 2004900800012 STATUS (COREL,20049007) used as a MONIT data 2004900800013 HISTORY (19710708A) correction made in comments 2004900800014 (19710908E) 2004900800015 (19860620U)HH 2004900800016 (19860703E) 2004900800017 (20120708A) SD: SF8=RNV was added in REACTION code. 2004900800018 ENDBIB 16 0 2004900800019 NOCOMMON 0 0 2004900800020 DATA 3 1 2004900800021 EN-MIN DATA DATA-ERR 2004900800022 KEV B B 2004900800023 5.0000E-04 1.0700E+01 2.5000E+00 2004900800024 ENDDATA 3 0 2004900800025 ENDSUBENT 24 0 2004900899999 SUBENT 20049009 20120708 22322004900900001 BIB 5 10 2004900900002 REACTION (27-CO-59(N,G)27-CO-60,,RI,,,DERIV) 2004900900003 DECAY-DATA (27-CO-60-M,10.4MIN) 2004900900004 REL-REF (A,11739002,E.Johnston+,J,JNE/A,11,95,1960) 2004900900005 This value compares well with the result 75+-5 barns 2004900900006 by Johnston et al., J.Nucl.Energy, A11(1960)95 and the2004900900007 73+-5 barns by Eastwood et al., Chalk river report 2004900900008 CI-207, unpublished. 2004900900009 STATUS (DEP,20049004) .If one includes the 1/v part one gets 2004900900010 72.3+-5.0 barns. 2004900900011 HISTORY (20120708C) SD 2004900900012 ENDBIB 10 0 2004900900013 NOCOMMON 0 0 2004900900014 DATA 3 1 2004900900015 EN-MIN DATA DATA-ERR 2004900900016 KEV B B 2004900900017 5.0000E-04 72.3 5. 2004900900018 ENDDATA 3 0 2004900900019 ENDSUBENT 18 0 2004900999999 SUBENT 20049010 20120708 22322004901000001 BIB 4 11 2004901000002 REACTION (29-CU-0(N,G),,RI,,RNV,DERIV) 2004901000003 REL-REF (D,20638016,R.B.Tattersall+,J,JNE/A,12,32,1960) 2004901000004 STATUS (DEP,20049005) 2004901000005 (DEP,20049006) .The resonance activation integral of 2004901000006 natural copper is calculated to be 2.56 +- 0.15 barns 2004901000007 from the values for Cu-63 and Cu-65. 2004901000008 This is significantly higher than the recent result 2004901000009 1.2 +- 0.5 barns obtained for the resonance 2004901000010 absorption integral by Tattersall et al. 2004901000011 J.Nucl.Energy, 12(1960)32. 2004901000012 HISTORY (20120708C) SD 2004901000013 ENDBIB 11 0 2004901000014 NOCOMMON 0 0 2004901000015 DATA 3 1 2004901000016 EN-MIN DATA DATA-ERR 2004901000017 KEV B B 2004901000018 5.0000E-04 2.56 0.15 2004901000019 ENDDATA 3 0 2004901000020 ENDSUBENT 19 0 2004901099999 ENDENTRY 10 0 2004999999999