ENTRY 40083 20221014 420940083 0 1 SUBENT 40083001 20221014 420940083 1 1 BIB 6 35 40083 1 2 TITLE Cross sections of the fast-neutron reactions (n,gamma) 40083 1 3 and (n,2n) for Re isotopes 40083 1 4 AUTHOR (A.A.Druzhinin,A.A.Lbov,L.P.Bilibin) 40083 1 5 REFERENCE (J,SNP,5,13,1967) Engl.transl. of YF,5,18,1967 40083 1 6 (J,YF,5,18,1967) Issue 1. 40083 1 7 INSTITUTE (4RUSKUR) 40083 1 8 METHOD (ACTIV) 40083 1 9 Absolute activity of Re-186, Re-188, Au-198, Na-24 was40083 1 10 defined by 4PI-counting method by proportional 40083 1 11 methane-filled flow-type counter. 40083 1 12 Absolute activity of Re-184, Re-184-M was defined from40083 1 13 gammas of 895. and 904 keV registered by scintillation 40083 1 14 gamma spectrometer with NaI(Tl) crystal of 900-keV 40083 1 15 gamma registration efficiency (1.00+-0.05) % . 40083 1 16 The identification of activities was done by HLs, 40083 1 17 gamma-spectra, absorption curves in Al, beta spectra 40083 1 18 from scin. beta spectrometer. 40083 1 19 HISTORY (19780712C) 40083 1 20 (19830724U) Corrections introduced 40083 1 21 (19840723U) New corrections introduced 40083 1 22 (19901207U) Corrections were made in Subents with 40083 1 23 multiple reaction formalism and minor errors corrected 40083 1 24 (19911025U) Data with multiple reaction formalism 40083 1 25 formerly given in one Subent are now given in 40083 1 26 various ones 40083 1 27 (20010311U) Dates and BIB-information corrected 40083 1 28 (20010726A) Corrected at CJD 40083 1 29 (20010726U) Last checking has been done. 40083 1 30 (20141115U) SD: Page of ref. of SNP corrected (3 -> 13)40083 1 31 ERR-T -> DATA-ERR in all Subents. 40083 1 32 (20150911U) M.M. Article was checked, BIB information 40083 1 33 was updated in TITLE,INC-SPECT,ANALYSIS,MONITOR,METHOD,40083 1 34 CORRECTION,SAMPLE,FLAG,STATUS,DECAY-DATA,REL-REF 40083 1 35 (20221014A) ERR-ANALYS and DECAY-DATA were moved in 40083 1 36 data Subents. 40083 1 37 ENDBIB 35 0 40083 1 38 NOCOMMON 0 0 40083 1 39 ENDSUBENT 38 0 40083 199999 SUBENT 40083002 20221014 420940083 2 1 BIB 15 25 40083 2 2 REACTION (75-RE-185(N,G)75-RE-186,,SIG,,SPA) 40083 2 3 INC-SPECT Two different spectra, both close to the spectrum of40083 2 4 fission neutrons. Neutron flux ~10**14 n/cm2; 40083 2 5 irradiation time 3-6 hr. 40083 2 6 DETECTOR (PROPC) 4PI methane-filled flow-type counter for B- 40083 2 7 DECAY-DATA (75-RE-186,,B-) 40083 2 8 MONITOR (79-AU-197(N,G)79-AU-198,,SIG,,FST) 40083 2 9 DECAY-MON (79-AU-198,,B-) 40083 2 10 MONIT-REF (11450001,D.J.Hughes+,J,PR,75,1781,1949) 40083 2 11 INC-SOURCE .No information 40083 2 12 SAMPLE (75-RE-185,ENR=0.808) Enriched, Re-185 content is 80.8%40083 2 13 .Also natural sample . 40083 2 14 CORRECTION .Correction for Re-187(n,2n) reaction 40083 2 15 FLAG (1.) Average of two relative measurements with 40083 2 16 - natural sample - 405+-45 mb, 40083 2 17 - enriched sample - 410+-50 mb. 40083 2 18 (2.) natural sample, relative method. 40083 2 19 ANALYSIS EN-DUMMY means the energy of monoenergetic neutrons, 40083 2 20 at which the CS of (n,gamma) reaction is equal to the 40083 2 21 cross section obtained with neutron spectrum. 40083 2 22 ERR-ANALYS (DATA-ERR) Error of monitor cross-section was included40083 2 23 STATUS (TABLE) Table I of J,SNP,5,13,1967 40083 2 24 HISTORY (20010726A) Merged with Subent 003. 40083 2 25 BIB-Information added 40083 2 26 (20010726U) Last checking has been done. 40083 2 27 ENDBIB 25 0 40083 2 28 NOCOMMON 0 0 40083 2 29 DATA 6 2 40083 2 30 EN-DUMMY DATA DATA-ERR MONIT MONIT-ERR FLAG 40083 2 31 MEV MB MB MB MB NO-DIM 40083 2 32 0.6 410. 50. 190. 19. 1. 40083 2 33 0.8 360. 50. 140. 10. 2. 40083 2 34 ENDDATA 4 0 40083 2 35 ENDSUBENT 34 0 40083 299999 NOSUBENT 40083003 19980303 420940083 3 1 SUBENT 40083004 20221014 420940083 4 1 BIB 15 36 40083 4 2 REACTION 1(75-RE-185(N,2N)75-RE-184-M,,SIG,,AV) 40083 4 3 2(75-RE-185(N,2N)75-RE-184-M,,SIG) 40083 4 4 3(75-RE-185(N,2N)75-RE-184-M,,SIG) 40083 4 5 FACILITY (LINAC,4RUSKUR) Deuterium accelerator, 40083 4 6 beam energy 150 keV. 40083 4 7 INC-SOURCE (D-T) Deuterons of 150 keV. 40083 4 8 INC-SPECT Neutron flux ~10**13 n/cm2 during irradiation of ~8hr.40083 4 9 The effective flux was determined from induced beta 40083 4 10 activity of Zr and Al samples. 40083 4 11 SAMPLE (75-RE-185,ENR=0.808) Enriched, Re-185 content is 80.8%40083 4 12 DETECTOR (NAICR) Gamma spectrometer with NaI(Tl) crystal of 40083 4 13 40x40 mm. 40083 4 14 DECAY-DATA (75-RE-184-M,,DG,895.,0.50,DG,904.,0.50) 40083 4 15 Value of 50% was used for Re-184m, taking into account40083 4 16 the yield of 0-30% in the decay of metastable state of40083 4 17 Re-184m directly to excited levels of W-184 from 40083 4 18 REL-REF : 40083 4 19 REL-REF (R,,B.Harmatz+,J,NP,56,1,1964) 40083 4 20 MONITOR 2((MONIT)13-AL-27(N,A)11-NA-24,,SIG) 40083 4 21 For relative measurement. 40083 4 22 3(92-U-238(N,F),,SIG) For neutron flux monitoring 40083 4 23 DECAY-MON 2(11-NA-24,,B-) 40083 4 24 ANALYSIS 1 Average of four measurements: 40083 4 25 2 two by relative method - 250+-100 mb, 270 +- 90 mb; 40083 4 26 3 two by absolute method - 270+-110 mb, 240 +-110 mb. 40083 4 27 CORRECTION Correction for fluctuation of neutron flux was 40083 4 28 determined by numerical integration and was < 0.8 %. 40083 4 29 ERR-ANALYS1(DATA-ERR) Type of uncertainty is not explained in the 40083 4 30 article. 40083 4 31 2(DATA-ERR) Error of monitor cross-section was included 40083 4 32 3(DATA-ERR) Type of uncertainty is not explained in the 40083 4 33 article. 40083 4 34 STATUS (TABLE) Table I of J,SNP,5,13,1967 40083 4 35 HISTORY (20010726U) BIB-information added 40083 4 36 (20010726U) Last checking has been done. 40083 4 37 (20221014A) AV was added in REACTION 1. 40083 4 38 ENDBIB 36 0 40083 4 39 COMMON 1 3 40083 4 40 EN 40083 4 41 MEV 40083 4 42 14.8 40083 4 43 ENDCOMMON 3 0 40083 4 44 DATA 8 2 40083 4 45 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MONIT 2MONIT-ERR 240083 4 46 DATA 3DATA-ERR 3 40083 4 47 MB MB MB MB MB MB 40083 4 48 MB MB 40083 4 49 260. 100. 250. 100. 117. 10. 40083 4 50 270. 110. 40083 4 51 270. 90. 117. 10. 40083 4 52 240. 110. 40083 4 53 ENDDATA 8 0 40083 4 54 ENDSUBENT 53 0 40083 499999 SUBENT 40083005 20221014 420940083 5 1 BIB 14 34 40083 5 2 REACTION 1(75-RE-185(N,2N)75-RE-184,,SIG,,AV) 40083 5 3 2(75-RE-185(N,2N)75-RE-184,,SIG) 40083 5 4 3(75-RE-185(N,2N)75-RE-184,,SIG) 40083 5 5 FACILITY (LINAC,4RUSKUR) Deuterium accelerator, 40083 5 6 beam energy 150 keV. 40083 5 7 DETECTOR (NAICR) Gamma spectrometer with NaI(Tl) crystal of 40083 5 8 40x40 mm. 40083 5 9 DECAY-DATA (75-RE-184,,DG,895.,0.148,DG,904.,0.445) 40083 5 10 From N.G.Gusev+, Radioactivnye izotopy kak 40083 5 11 gamma-izluchenie ( Radioactive Isotopes as 40083 5 12 gamma-emitters), Atomizdat, 1964. 40083 5 13 INC-SOURCE (D-T) 40083 5 14 INC-SPECT Neutron flux ~10**13 n/cm2 during irradiation of ~8hr.40083 5 15 The effective flux was determined from induced beta 40083 5 16 activity of Zr and Al samples. 40083 5 17 SAMPLE (75-RE-185,ENR=0.808) Enriched, Re-185 content is 80.8%40083 5 18 MONITOR 2((MONIT)13-AL-27(N,A)11-NA-24,,SIG) 40083 5 19 For relative measurement. 40083 5 20 3(92-U-238(N,F),,SIG) For neutron flux monitoring 40083 5 21 DECAY-MON 2(11-NA-24,,B-) 40083 5 22 ANALYSIS 1 Average of four measurements: 40083 5 23 2- two by relative method - 1430+-220 mb, 1450+-220 mb, 40083 5 24 3- two by absolute method - 1520+-230 mb, 1300+-200 mb. 40083 5 25 CORRECTION Correction for fluctuation of neutron flux was 40083 5 26 determined by numerical integration and was < 0.8 %. 40083 5 27 ERR-ANALYS1(DATA-ERR) Type of uncertainty is not explained in the 40083 5 28 article. 40083 5 29 2(DATA-ERR) Error of monitor cross-section was included 40083 5 30 3(DATA-ERR) Type of uncertainty is not explained in the 40083 5 31 article. 40083 5 32 STATUS (TABLE) Table I of J,SNP,5,13,1967 40083 5 33 HISTORY (20010726U) BIB-information added 40083 5 34 (20010726U) Last checking has been done. 40083 5 35 (20221014A) AV was added in REACTION 1. 40083 5 36 ENDBIB 34 0 40083 5 37 COMMON 1 3 40083 5 38 EN 40083 5 39 MEV 40083 5 40 14.8 40083 5 41 ENDCOMMON 3 0 40083 5 42 DATA 8 2 40083 5 43 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MONIT 2MONIT-ERR 240083 5 44 DATA 3DATA-ERR 3 40083 5 45 MB MB MB MB MB MB 40083 5 46 MB MB 40083 5 47 1430. 220. 1430. 220. 117. 10. 40083 5 48 1520. 230. 40083 5 49 1450. 220. 117. 10. 40083 5 50 1300. 200. 40083 5 51 ENDDATA 8 0 40083 5 52 ENDSUBENT 51 0 40083 599999 SUBENT 40083006 20221014 420940083 6 1 BIB 14 22 40083 6 2 REACTION (75-RE-187(N,G)75-RE-188,,SIG,,SPA) 40083 6 3 DETECTOR (PROPC) 4PI methane-filled flow-type counter for B- 40083 6 4 DECAY-DATA (75-RE-188,,B-) 40083 6 5 MONITOR (79-AU-197(N,G)79-AU-198,,SIG,,SPA) 40083 6 6 DECAY-MON (79-AU-198,,B-) 40083 6 7 MONIT-REF (11450001,D.J.Hughes+,J,PR,75,1781,1949) 40083 6 8 INC-SOURCE .No information 40083 6 9 INC-SPECT Two different spectra, both close to the spectrum of40083 6 10 fission neutrons. Neutron flux ~10**14 n/cm2; 40083 6 11 irradiation time 3-6 hr. 40083 6 12 SAMPLE (75-RE-187,ENR=0.975) Enriched, Re-187 content is 97.5%40083 6 13 .Also natural sample. 40083 6 14 FLAG (1.) Average of two measurements by relative method: 40083 6 15 - with natural sample 280+-30 mb; 40083 6 16 - with enriched sample 285+-30 mb. 40083 6 17 ANALYSIS EN-DUMMY means the energy of monoenergetic neutrons, 40083 6 18 at which the CS of (n,gamma) reaction is equal to the 40083 6 19 cross section obtained with neutron spectrum. 40083 6 20 ERR-ANALYS (DATA-ERR) Error of monitor cross-section was included40083 6 21 STATUS (TABLE) Table I of J,SNP,5,13,1967 40083 6 22 HISTORY (20010726U) BIB-information added; data corrected 40083 6 23 (20010726U) Last checking has been done. 40083 6 24 ENDBIB 22 0 40083 6 25 NOCOMMON 0 0 40083 6 26 DATA 6 2 40083 6 27 EN-DUMMY DATA DATA-ERR MONIT MONIT-ERR FLAG 40083 6 28 MEV MB MB MB MB NO-DIM 40083 6 29 0.6 280. 30. 190. 19. 1. 40083 6 30 0.8 220. 10. 140. 10. 40083 6 31 ENDDATA 4 0 40083 6 32 ENDSUBENT 31 0 40083 699999 SUBENT 40083007 20221014 420940083 7 1 BIB 11 18 40083 7 2 REACTION (75-RE-187(N,2N)75-RE-186,,SIG,,SPA) 40083 7 3 DETECTOR (PROPC) 4PI methane-filled flow-type counter for B- 40083 7 4 DECAY-DATA (75-RE-186,,B-) 40083 7 5 MONITOR (79-AU-197(N,G)79-AU-198,,SIG,,SPA) 40083 7 6 DECAY-MON (79-AU-198,,B-) 40083 7 7 INC-SPECT Similar to the fission spectrum 40083 7 8 SAMPLE (75-RE-187,ENR=0.975) Enriched, Re-187 content is 97.5%40083 7 9 ANALYSIS Measurement with enriched sample by relative method. 40083 7 10 EN-DUMMY means the energy of monoenergetic neutrons, 40083 7 11 at which the CS of (n,gamma) reaction is equal to the 40083 7 12 cross section obtained with neutron spectrum. 40083 7 13 ERR-ANALYS (DATA-ERR) Error of monitor cross-section was included40083 7 14 STATUS (TABLE) Table I of J,SNP,5,13,1967 40083 7 15 HISTORY (20010726U) BIB-information added 40083 7 16 (20010726U) Last checking has been done. 40083 7 17 (20221014A) Monitor was corrected: 40083 7 18 13-AL-27(N,A)11-NA-24,,SIG -> 40083 7 19 79-AU-197(N,G)79-AU-198,,SIG,,SPA 40083 7 20 ENDBIB 18 0 40083 7 21 NOCOMMON 0 0 40083 7 22 DATA 5 1 40083 7 23 EN-DUMMY DATA DATA-ERR MONIT MONIT-ERR 40083 7 24 MEV MB MB MB MB 40083 7 25 0.6 10. 6. 190. 19. 40083 7 26 ENDDATA 3 0 40083 7 27 ENDSUBENT 26 0 40083 799999 SUBENT 40083008 20221014 420940083 8 1 BIB 14 32 40083 8 2 REACTION 1(75-RE-187(N,2N)75-RE-186,,SIG,,AV) 40083 8 3 2(75-RE-187(N,2N)75-RE-186,,SIG) 40083 8 4 3(75-RE-187(N,2N)75-RE-186,,SIG) 40083 8 5 SAMPLE (75-RE-187,ENR=0.975) Enriched, Re-187 content is 97.5%40083 8 6 FACILITY (LINAC,4RUSKUR) Deuterium accelerator, 40083 8 7 beam energy 150 keV. 40083 8 8 DETECTOR (PROPC) 4PI methane-filled flow-type counter for B- 40083 8 9 DECAY-DATA (75-RE-186,,B-) 40083 8 10 INC-SOURCE (D-T) 40083 8 11 INC-SPECT Neutron flux ~10**13 n/cm2 during irradiation of ~8hr.40083 8 12 The effective flux was determined from induced beta 40083 8 13 activity of Zr and Al samples. 40083 8 14 MONITOR 2((MONIT)13-AL-27(N,A)11-NA-24,,SIG) 40083 8 15 For relative measurements. 40083 8 16 3(92-U-238(N,F),,SIG) For neutron flux monitoring 40083 8 17 DECAY-MON 2(11-NA-24,,B-) 40083 8 18 ANALYSIS 1 Average of 6 measurements with enriched sample: 40083 8 19 2- 3 by relative method - 1440+-140 mb, 1540+-140 mb, 40083 8 20 1460+-130 mb; 40083 8 21 3- 3 by absolute method - 1480+-150 mb, 1420+-130 mb, 40083 8 22 1620+-170 mb. 40083 8 23 CORRECTION Correction for fluctuation of neutron flux was 40083 8 24 determined by numerical integration and was < 0.8 %. 40083 8 25 ERR-ANALYS1(DATA-ERR) Type of uncertainty is not explained in the 40083 8 26 article. 40083 8 27 2(DATA-ERR) Error of monitor cross-section was included 40083 8 28 3(DATA-ERR) Type of uncertainty is not explained in the 40083 8 29 article. 40083 8 30 STATUS (TABLE) Table I of J,SNP,5,13,1967 40083 8 31 HISTORY (20010726U) BIB-information added 40083 8 32 (20010726U) Last checking has been done. 40083 8 33 (20221014A) AV was added in REACTION 1. 40083 8 34 ENDBIB 32 0 40083 8 35 COMMON 1 3 40083 8 36 EN 40083 8 37 MEV 40083 8 38 14.8 40083 8 39 ENDCOMMON 3 0 40083 8 40 DATA 8 3 40083 8 41 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MONIT 2MONIT-ERR 240083 8 42 DATA 3DATA-ERR 3 40083 8 43 MB MB MB MB MB MB 40083 8 44 MB MB 40083 8 45 1490. 160. 1440. 140. 117. 10.40083 8 46 1480. 150. 40083 8 47 1540. 140. 117. 10.40083 8 48 1420. 130. 40083 8 49 1460. 130. 117. 10.40083 8 50 1620. 170. 40083 8 51 ENDDATA 10 0 40083 8 52 ENDSUBENT 51 0 40083 899999 SUBENT 40083009 20221014 420940083 9 1 BIB 14 31 40083 9 2 REACTION (75-RE-0(N,G),,SIG,,SPA) 40083 9 3 REL-REF (A,40691002,Yu.Ya.Stavisskii+,J,SJA,19,905,1965) 40083 9 4 Calculated value 289 mb at Eeff=0.8 MeV - by using 40083 9 5 the data of 40691. 40083 9 6 325+-60 mb and 290+-60 mb at monoenergetic neutrons 40083 9 7 of 0.6+-0.1 and 0.8+-0.1 MeV energy,respectively. 40083 9 8 SAMPLE Natural rhenium 40083 9 9 INC-SOURCE .No information 40083 9 10 INC-SPECT Two different spectra, both close to the spectrum of40083 9 11 fission neutrons. Neutron flux ~10**14 n/cm2; 40083 9 12 irradiation time 3-6 hr. 40083 9 13 DETECTOR (PROPC) 4PI methane-filled flow-type counter for B- 40083 9 14 MONITOR (79-AU-197(N,G)79-AU-198,,SIG,,SPA) 40083 9 15 DECAY-MON (79-AU-198,,B-) 40083 9 16 MONIT-REF (11450001,D.J.Hughes+,J,PR,75,1781,1949) 40083 9 17 ANALYSIS .EN-DUMMY means the energy of monoenergetic neutrons, 40083 9 18 at which the CS of (n,gamma) reaction is equal to the 40083 9 19 cross section obtained with neutron spectrum. 40083 9 20 . Formula and explanation ( how to derive cross-section40083 9 21 for Re-nat) are not given in the article; cross-section40083 9 22 is just mentioned as "measured by authors". 40083 9 23 COMMENT Of N.Otsuka ( NDS, IAEA). 40083 9 24 "The cross sections are equal to the sum of the 185Re 40083 9 25 and 187Re neutron capture cross sections measured in 40083 9 26 this work (40083.002 and 006) weighted by their 40083 9 27 natural isotopic abundances." 40083 9 28 ERR-ANALYS (DATA-ERR) Error of monitor cross-section was included40083 9 29 STATUS (TABLE) Table II of J,SNP,5,13,1967 40083 9 30 HISTORY (20010726U) BIB-information added 40083 9 31 (20010726U) Last checking has been done. 40083 9 32 (20150911A) M.M. MONIT-ERR for 0.8 MeV was corrected. 40083 9 33 ENDBIB 31 0 40083 9 34 NOCOMMON 0 0 40083 9 35 DATA 5 2 40083 9 36 EN-DUMMY DATA DATA-ERR MONIT MONIT-ERR 40083 9 37 MEV MB MB MB MB 40083 9 38 0.6 330. 40. 190. 19. 40083 9 39 0.8 270. 30. 140. 10. 40083 9 40 ENDDATA 4 0 40083 9 41 ENDSUBENT 40 0 40083 999999 ENDENTRY 9 0 4008399999999