ENTRY 40863 20240724 42184086300000001 SUBENT 40863001 20240724 42184086300100001 BIB 12 33 4086300100002 TITLE Cross section of the 111Cd(n,n')111mCd reaction in 4086300100003 the interval extending from the threshold energy to 4086300100004 2.2 MeV 4086300100005 AUTHOR (Yu.N.Trofimov) 4086300100006 REFERENCE (J,SJA,57,(3),670,1984) Engl. translation of J,AE . 4086300100007 #doi:10.1007/BF01122346 4086300100008 (J,AE,57,(3),210,198409) 4086300100009 INSTITUTE (4RUSRI) 4086300100010 FACILITY (VDG) 4086300100011 INC-SOURCE (P-T) T-Ti targets . 4086300100012 SAMPLE Cd-110 content is 0.35 %, Cd-111 content is 95.1 %, 4086300100013 Cd-112 content is 2.98 %, Cd-113 content is 0.48 %, 4086300100014 Cd-114 content is 0.93 %, Cd-116 content is 0.16 %. 4086300100015 Sample mass 20 mg, diameter 6 mm. 4086300100016 METHOD (ACTIV) 4086300100017 DETECTOR (SOLST) Two detectors of diameter 6mm , thickness 0.2mm4086300100018 to measure neutron flux. 4086300100019 (SPEC,GELI) Ge(Li) spectrometer with detector of 4086300100020 38 cm**3 volume, resolution 3 keV for 1332 keV line, 4086300100021 to measure energy and intensity of gamma-peaks. 4086300100022 Spectrometer was calibrated by standard sources. 4086300100023 CORRECTION On scattered neutrons - 3+-1 % , on pulse addition - 4086300100024 1.5+-0.3 % , 4086300100025 ERR-ANALYS (ERR-1) Error due to the Ge-Li detector efficiency 4086300100026 (ERR-2) Cd-111-m activity error 4086300100027 (ERR-3) In-116-m activity error 4086300100028 (ERR-T) Total error. 4086300100029 HISTORY (19850521C) 4086300100030 (20110715A) M.M. Upper -> lower case correction. 4086300100031 Dates were corrected for 4-digits year. 4086300100032 BIB information was added. 4086300100033 Ref. J,SJA was added. 4086300100034 (20240724U) Subent 002 was corrected. 4086300100035 ENDBIB 33 0 4086300100036 COMMON 3 3 4086300100037 ERR-1 ERR-2 ERR-3 4086300100038 PER-CENT PER-CENT PER-CENT 4086300100039 4. 0.5 1. 4086300100040 ENDCOMMON 3 0 4086300100041 ENDSUBENT 40 0 4086300199999 SUBENT 40863002 20240724 42184086300200001 BIB 9 24 4086300200002 REACTION (48-CD-111(N,INL)48-CD-111-M,,SIG) 4086300200003 DECAY-DATA (48-CD-111-M,49.1MIN,DG,245.35,0.942) 4086300200004 MONITOR (49-IN-115(N,G)49-IN-116-M1+M2,,SIG) 4086300200005 IT=100% for M2 -> M1 4086300200006 (49-IN-115(N,INL)49-IN-115-M,,SIG) 4086300200007 DECAY-MON (49-IN-115-M,,DG,336.25) 4086300200008 (49-IN-116-M1,54.15MIN,DG,416.98,0.33) 4086300200009 54.15+-0.05 min, 0.33+-0.01 - data from REL-REF. 4086300200010 MONIT-REF (,,R,BNL-NCS-50446,1975) ENDF/B-V Dosimetry File. 4086300200011 REL-REF (R,,N.G.Gusev+,B,GUSEV,,,1977) Ref. for DECAY-MON data.4086300200012 COMMENT Of compiler M.M. 4086300200013 Data at En=0.3 MeV is given in the Table of the 4086300200014 article as 0. +- 0. mb; the total absolute uncertainty 4086300200015 (= 0.mb) looks like strange, even point is below the 4086300200016 reaction threshold (0.4 MeV mentioned in the article). 4086300200017 ERR-T at this data point was deleted because this 4086300200018 point is below the reaction threshold and ERR-2 4086300200019 (Cd-111-m activity error = 0.5 %) could not be 4086300200020 applied at this case ( no activation is supposed below4086300200021 threshold). 4086300200022 STATUS (TABLE,,Yu.N.Trofimov,J,SJA,57,(3),670,1984) 4086300200023 Table on page 671 4086300200024 HISTORY (20240724A) ERR-T = 0. mb at En=0.3 MeV was deleted - 4086300200025 see comment of compiler. 4086300200026 ENDBIB 24 0 4086300200027 COMMON 2 3 4086300200028 ERR-HL ERR-IDD 4086300200029 MIN NO-DIM 4086300200030 0.1 0.001 4086300200031 ENDCOMMON 3 0 4086300200032 DATA 6 14 4086300200033 EN EN-RSL-FW DATA ERR-T MONIT1 MONIT2 4086300200034 MEV MEV MB MB MB MB 4086300200035 0.3 .14 0. 180. 0. 4086300200036 0.5 .13 0.3 0.1 183. 3.75 4086300200037 0.7 .13 8. 1. 190. 14. 4086300200038 0.8 .13 25. 2. 200. 23. 4086300200039 1.0 .12 62. 5. 188. 59. 4086300200040 1.2 .11 103. 8. 178. 101. 4086300200041 1.4 .10 150. 12. 160. 136. 4086300200042 1.5 .10 174. 14. 160. 167. 4086300200043 1.6 .09 205. 16. 153. 189. 4086300200044 1.8 .09 236. 17. 137. 232. 4086300200045 1.9 .09 248. 18. 129. 246. 4086300200046 2.0 .08 220. 17. 121. 260. 4086300200047 2.1 .08 232. 18. 115. 270. 4086300200048 2.2 .08 253. 20. 108. 280. 4086300200049 ENDDATA 16 0 4086300200050 ENDSUBENT 49 0 4086300299999 ENDENTRY 2 0 4086399999999