ENTRY 11923 20140413 14011192300000001 SUBENT 11923001 20140413 14011192300100001 BIB 13 27 1192300100002 INSTITUTE (1USAPPO) 1192300100003 REFERENCE (J,NP,75,215,196601) 1192300100004 AUTHOR (P.R.Gray,A.R.Zander,T.G.Ebrey) 1192300100005 TITLE Activation cross sections for reactions of Rh and Ru 1192300100006 with 14.7 MeV neutrons. 1192300100007 FACILITY (CCW,1USAPPO) 1192300100008 INC-SOURCE (D-T) Neutron source strengths of 10**9 to 1192300100009 5 x 10**10 DT neutrons/sec x 4Pi 1192300100010 SAMPLE Powdered samples of rhodium and ruthenium in 1192300100011 5 ml polystyrene. In irradiations of enriched 1192300100012 ruthenium isotopes, powdered Al(2)O(3) was thoroughly 1192300100013 mixed with each sample prior to irradiation to surmount1192300100014 the difficulty of exact reproduction of the geometry in1192300100015 irradiations of milligram quantities of materials. 1192300100016 DETECTOR (NAICR) 7.6 cm x 7.6 cm NaI(TI) crystal scintillation 1192300100017 spectrometer and a 400-channel transistorized analyser1192300100018 METHOD (ACTIV,RCHEM) Activation 1192300100019 MONITOR ((MONIT1)29-CU-63(N,2N)29-CU-62,,SIG) 1192300100020 ((MONIT2)13-AL-27(N,A)11-NA-24,,SIG) 1192300100021 MONIT-REF ((MONIT1)11356001,J.M.Ferguson+,J,PR,118,228,1960) 1192300100022 ((MONIT2)11196001,J.Kantele+,J,NP,35,353,1962) 1192300100023 STATUS (TABLE) Tbl.1 from NP,75,215 1192300100024 HISTORY (19760802T) Translated from SCISRS 1192300100025 (19830802A) converted to reaction formalism 1192300100026 (20140413A) SD: Updated to new date formats,lower case.1192300100027 Corrections according last EXFOR rules and Dict. 1192300100028 REACTION code corrected in Subents 2,4. BIB updated. 1192300100029 ENDBIB 27 0 1192300100030 COMMON 2 3 1192300100031 MONIT1 MONIT2 1192300100032 MB MB 1192300100033 507. 82. 1192300100034 ENDCOMMON 3 0 1192300100035 ENDSUBENT 34 0 1192300199999 SUBENT 11923002 20140413 14011192300200001 BIB 5 13 1192300200002 REACTION (44-RU-96(N,X)43-TC-95,CUM,SIG) 1192300200003 DECAY-DATA (44-RU-95,99.MIN) 1192300200004 (43-TC-95-G,20.HR,DG,768.,0.845) 1192300200005 ANALYSIS The cross section for the 96Ru(n,2n)95Ru reaction was 1192300200006 measured by determining the amount of 20 h 95Tc that 1192300200007 grew in from the 99 min 95Ru during irradiation and 1192300200008 before chemical separation of the technetium fraction 1192300200009 was completed. 1192300200010 ERR-ANALYS (DATA-ERR) The standard deviation is an estimate of 1192300200011 the errors and uncertainties involved in the 1192300200012 measured quantities 1192300200013 HISTORY (20140413A) SD: REACTION code corrected: 1192300200014 96Ru(n,d)+96Ru(n,n+p) -> 96Ru(n,x). COMMENT deleted. 1192300200015 ENDBIB 13 0 1192300200016 NOCOMMON 0 0 1192300200017 DATA 4 1 1192300200018 EN EN-RSL DATA DATA-ERR 1192300200019 MEV MEV B B 1192300200020 1.47E+01 5.E-01 2.6 3.E-01 1192300200021 ENDDATA 3 0 1192300200022 ENDSUBENT 21 0 1192300299999 SUBENT 11923003 20140413 14011192300300001 BIB 5 10 1192300300002 REACTION (44-RU-96(N,P)43-TC-96,,SIG) 1192300300003 DECAY-DATA (43-TC-96-G,4.3D,DG,770./804./840.,0.028) 1192300300004 COMMENT The cross section for the 96Ru(n,p)96Tc reaction was 1192300300005 calculated assuming a total branching ratio (see 1192300300006 Nuclear Data Sheets) of 2.8 for the integrated peaks 1192300300007 of the three gammas of 96Tc. 1192300300008 ERR-ANALYS (DATA-ERR) The standard deviation is an estimate of 1192300300009 the errors and uncertainties involved in the 1192300300010 measured quantities 1192300300011 HISTORY (20140413A) SD: COMMENT was added. 1192300300012 ENDBIB 10 0 1192300300013 NOCOMMON 0 0 1192300300014 DATA 4 1 1192300300015 EN EN-RSL DATA DATA-ERR 1192300300016 MEV MEV B B 1192300300017 1.47E+01 5.E-01 1.70E-01 3.0E-02 1192300300018 ENDDATA 3 0 1192300300019 ENDSUBENT 18 0 1192300399999 SUBENT 11923004 20140413 14011192300400001 BIB 5 13 1192300400002 REACTION (44-RU-0(N,X)43-TC-99-M,,SIG) 1192300400003 DECAY-DATA (43-TC-99-M,6.HR,DG,142.) 1192300400004 COMMENT The contribution from 100Ru(n,d)99mTc could not be 1192300400005 measured; hence only the total cross section for the 1192300400006 reactions 99Ru(n,p)99mTc+ 100Ru(n,d)99mTc was 1192300400007 determined. Assuming an internal conversion 1192300400008 coefficient (see Nuclear Data Sheets) of 0.095 for the 1192300400009 142 keV gamma this total cross section was determined. 1192300400010 ERR-ANALYS (DATA-ERR) The standard deviation is an estimate of 1192300400011 the errors and uncertainties involved in the 1192300400012 measured quantities 1192300400013 HISTORY (20140413A) SD: REACTION code corrected: 1192300400014 99Ru(n,p)+100Ru(n,d) -> Ru(n,x). COMMENT was added. 1192300400015 ENDBIB 13 0 1192300400016 NOCOMMON 0 0 1192300400017 DATA 4 1 1192300400018 EN EN-RSL DATA-MAX DATA-ERR 1192300400019 MEV MEV B B 1192300400020 1.47E+01 5.E-01 1.6E-02 4.E-03 1192300400021 ENDDATA 3 0 1192300400022 ENDSUBENT 21 0 1192300499999 SUBENT 11923005 20140413 14011192300500001 BIB 6 9 1192300500002 REACTION (44-RU-0(N,X)43-TC-101,,SIG) 1192300500003 DECAY-DATA (43-TC-101,14.MIN,DG,307.,0.91) 1192300500004 ANALYSIS contribution of 104Ru(n,alpha) was taken into account 1192300500005 ERR-ANALYS (DATA-ERR) The standard deviation is an estimate of 1192300500006 the errors and uncertainties involved in the 1192300500007 measured quantities 1192300500008 STATUS (DEP,11923006) 1192300500009 HISTORY (20140413A) SD: ANALYSIS, STATUS added. REACTION code 1192300500010 corrected: 101Ru(n,p)+102Ru(n,d) -> Ru(n,x). 1192300500011 ENDBIB 9 0 1192300500012 NOCOMMON 0 0 1192300500013 DATA 4 1 1192300500014 EN EN-RSL DATA DATA-ERR 1192300500015 MEV MEV B B 1192300500016 1.47E+01 5.E-01 3.6E-02 3.E-03 1192300500017 ENDDATA 3 0 1192300500018 ENDSUBENT 17 0 1192300599999 SUBENT 11923006 20140413 14011192300600001 BIB 7 14 1192300600002 REACTION (44-RU-104(N,A)42-MO-101,,SIG) 1192300600003 SAMPLE (44-RU-104,ENR=0.9639) 1192300600004 COMMENT The weighted average cross section from two gamma 1192300600005 spectra taken at different times after the end of the 1192300600006 irradiation assuming a branching ratio of 0.91 for 1192300600007 the 0.307 MeV radiation. 1192300600008 DECAY-DATA (43-TC-101,14.6MIN,DG,307.,0.91) 1192300600009 ANALYSIS The cross section of this reaction was determined by 1192300600010 measuring 14 min 101Tc, which is the beta decay 1192300600011 daughter of 101Mo. 1192300600012 ERR-ANALYS (DATA-ERR) The standard deviation is an estimate of 1192300600013 the errors and uncertainties involved in the 1192300600014 measured quantities 1192300600015 HISTORY (20140413A) SD: ANALYSIS, COMMENT added. 1192300600016 ENDBIB 14 0 1192300600017 NOCOMMON 0 0 1192300600018 DATA 4 1 1192300600019 EN EN-RSL DATA DATA-ERR 1192300600020 MEV MEV B B 1192300600021 1.47E+01 5.E-01 2.6E-03 1.0E-03 1192300600022 ENDDATA 3 0 1192300600023 ENDSUBENT 22 0 1192300699999 SUBENT 11923007 20140413 14011192300700001 BIB 6 9 1192300700002 REACTION (44-RU-104(N,G)44-RU-105,,SIG) 1192300700003 SAMPLE (44-RU-104,ENR=0.9639) 1192300700004 DECAY-DATA (44-RU-105,4.4HR,DG,726.,0.48) 1192300700005 ERR-ANALYS (DATA-ERR) The standard deviation is an estimate of 1192300700006 the errors and uncertainties involved in the 1192300700007 measured quantities 1192300700008 COMMENT The thermal neutron yield was not great enough to 1192300700009 affect this result significantly. 1192300700010 HISTORY (20140413A) SD: ANALYSIS, COMMENT added. 1192300700011 ENDBIB 9 0 1192300700012 NOCOMMON 0 0 1192300700013 DATA 4 1 1192300700014 EN EN-RSL DATA DATA-ERR 1192300700015 MEV MEV B B 1192300700016 1.47E+01 5.E-01 2.5E-03 5.E-04 1192300700017 ENDDATA 3 0 1192300700018 ENDSUBENT 17 0 1192300799999 SUBENT 11923008 20140413 14011192300800001 BIB 6 13 1192300800002 REACTION (44-RU-104(N,P)43-TC-104,,SIG) 1192300800003 SAMPLE (44-RU-104,ENR=0.9639) 1192300800004 ANALYSIS Using a branching ratio of 0.72 for the 0.360 MeV gamma1192300800005 radiation and assuming no beta decay to the ground 1192300800006 state of 102Ru, the analysis of several 104Tc gamma 1192300800007 spectra taken at different times after the end of the 1192300800008 irradiation and from three separate neutron irradia- 1192300800009 tions gave a weighted average for the cross section. 1192300800010 DECAY-DATA (43-TC-104,18.MIN,DG,360.,0.72) 1192300800011 ERR-ANALYS (DATA-ERR) The standard deviation is an estimate of 1192300800012 the errors and uncertainties involved in the 1192300800013 measured quantities 1192300800014 HISTORY (20140413A) SD: ANALYSIS added. 1192300800015 ENDBIB 13 0 1192300800016 NOCOMMON 0 0 1192300800017 DATA 4 1 1192300800018 EN EN-RSL DATA DATA-ERR 1192300800019 MEV MEV B B 1192300800020 1.47E+01 5.E-01 7.2E-03 1.0E-03 1192300800021 ENDDATA 3 0 1192300800022 ENDSUBENT 21 0 1192300899999 SUBENT 11923009 20140413 14011192300900001 BIB 7 14 1192300900002 REACTION (44-RU-104(N,2N)44-RU-103,,SIG) 1192300900003 SAMPLE (44-RU-104,ENR=0.9639) 1192300900004 ANALYSIS The weighted average cross section for this reaction 1192300900005 from three separate neutron irradiations was defined, 1192300900006 using a branching ratio of 0.885 for the 0.498 MeV 1192300900007 gamma radiation. 1192300900008 COMMENT Since enriched 104Ru containing no 96Ru was used in 1192300900009 these measurements, no 4.3 d 96Tc or 20 h 95Ru was 1192300900010 made in the irradiation. 1192300900011 DECAY-DATA (44-RU-103,40.D,DG,498.,0.885) 1192300900012 ERR-ANALYS (DATA-ERR) The standard deviation is an estimate of 1192300900013 the errors and uncertainties involved in the 1192300900014 measured quantities 1192300900015 HISTORY (20140413A) SD: ANALYSIS, COMMENT added. 1192300900016 ENDBIB 14 0 1192300900017 NOCOMMON 0 0 1192300900018 DATA 4 1 1192300900019 EN EN-RSL DATA DATA-ERR 1192300900020 MEV MEV B B 1192300900021 1.47E+01 5.E-01 2.5 5.E-01 1192300900022 ENDDATA 3 0 1192300900023 ENDSUBENT 22 0 1192300999999 SUBENT 11923010 20140413 14011192301000001 BIB 8 17 1192301000002 REACTION (44-RU-102(N,P)43-TC-102-M,,SIG) 1192301000003 SAMPLE (44-RU-102,ENR=0.908) 1192301000004 ANALYSIS The cross section of the 102Ru(n,p)102Tc reaction was 1192301000005 calculated on the basis of the 102Ru level scheme (see 1192301000006 REL-REF) assuming no beta decay to the ground state of 1192301000007 102Ru. A branching ratio of 1.0 was used for the 1192301000008 0.475 MeV radiation, ignoring the 1.105 MeV crossover 1192301000009 radiation. 1192301000010 REL-REF (R,,A.R.Zander+,J,NP,75,209,1966) 1192301000011 DECAY-DATA (43-TC-102-M,4.5MIN,DG,475.,1.0) 1192301000012 COMMENT From the NP,75, p.221: No attempt was made to detect 1192301000013 any short-lived (5+-1 sec) activity of Tc-102g 1192301000014 ERR-ANALYS (DATA-ERR) The standard deviation is an estimate of 1192301000015 the errors and uncertainties involved in the 1192301000016 measured quantities 1192301000017 HISTORY (20140413A) SD: Tc-102 -> Tc-102m in REACTION code. 1192301000018 ANALYSIS,REL-REF and COMMENT were added. 1192301000019 ENDBIB 17 0 1192301000020 NOCOMMON 0 0 1192301000021 DATA 5 1 1192301000022 EN EN-RSL DATA +DATA-ERR -DATA-ERR 1192301000023 MEV MEV B B B 1192301000024 1.47E+01 5.E-01 6.7E-03 2.5E-03 1.0E-03 1192301000025 ENDDATA 3 0 1192301000026 ENDSUBENT 25 0 1192301099999 SUBENT 11923011 20140413 14011192301100001 BIB 5 13 1192301100002 REACTION (45-RH-103(N,N+A)43-TC-99-M,,SIG) 1192301100003 ANALYSIS Using two separate rhodium irradiations, and separate 1192301100004 monitor runs (copper and aluminium), as well as the 1192301100005 integrated peak areas from several spectra taken up to 1192301100006 8 h after irradiation, the cross section for the 1192301100007 103Rh(n,n'alpha)99mTc reaction is calculated, using a 1192301100008 conversion coefficient (see Nuclear Data Sheets) of 1192301100009 0.095 for the 142 keV radiation. 1192301100010 DECAY-DATA (43-TC-99-M,6.HR,DG,142.) 1192301100011 ERR-ANALYS (DATA-ERR) The standard deviation is an estimate of 1192301100012 the errors and uncertainties involved in the 1192301100013 measured quantities 1192301100014 HISTORY (20140413A) SD: ANALYSIS and REL-REF were added. 1192301100015 ENDBIB 13 0 1192301100016 NOCOMMON 0 0 1192301100017 DATA 4 1 1192301100018 EN EN-RSL DATA DATA-ERR 1192301100019 MEV MEV B B 1192301100020 1.47E+01 5.E-01 1.50E-04 3.0E-05 1192301100021 ENDDATA 3 0 1192301100022 ENDSUBENT 21 0 1192301199999 SUBENT 11923012 20140413 14011192301200001 BIB 4 4 1192301200002 REACTION (45-RH-103(N,HE3)43-TC-101,,SIG) 1192301200003 ANALYSIS Upper limit determined from Rh-103 (n,n'alpha). 1192301200004 STATUS (DEP,11923011) see ANALYSIS 1192301200005 HISTORY (20140413A) SD: STATUS added 1192301200006 ENDBIB 4 0 1192301200007 NOCOMMON 0 0 1192301200008 DATA 3 1 1192301200009 EN EN-RSL DATA-MAX 1192301200010 MEV MEV B 1192301200011 1.47E+01 5.E-01 4.E-07 1192301200012 ENDDATA 3 0 1192301200013 ENDSUBENT 12 0 1192301299999 SUBENT 11923013 20140413 14011192301300001 BIB 4 4 1192301300002 REACTION (45-RH-103(N,2P)43-TC-102,,SIG) 1192301300003 ANALYSIS Upper limit determined from Rh-103 (n,n'alpha). 1192301300004 STATUS (DEP,11923011) see ANALYSIS 1192301300005 HISTORY (20140413A) SD: STATUS added 1192301300006 ENDBIB 4 0 1192301300007 NOCOMMON 0 0 1192301300008 DATA 3 1 1192301300009 EN EN-RSL DATA-MAX 1192301300010 MEV MEV B 1192301300011 1.47E+01 5.E-01 3.0E-06 1192301300012 ENDDATA 3 0 1192301300013 ENDSUBENT 12 0 1192301399999 ENDENTRY 13 0 1192399999999