ENTRY 31746 20140924 31663174600000001 SUBENT 31746001 20140924 31663174600100001 BIB 18 49 3174600100002 TITLE Radiative capture cross sections of 155,157Gd for 3174600100003 thermal neutrons 3174600100004 AUTHOR (H.D.Choi, R.B.Firestone, M.S.Basunia, A.Hurst, 3174600100005 B.Sleaford, N.Summers, J.E.Escher, Zs.Revay, 3174600100006 L.Szentmiklosi, T.Belgya, M.Krticka) 3174600100007 INSTITUTE (1USABRK,1USALRL,3HUNKFI,3CZRCHU) 3174600100008 REFERENCE (J,NSE,177,219,2014) 3174600100009 EXP-YEAR (2010) 3174600100010 FACILITY (REAC,3HUNKFI) 10-MW Budapest Research Reactor 3174600100011 INC-SOURCE (REAC) Guided cold neutron beam. Flux was 3174600100012 1.2E+08 neutrons/cm2/sec at the sample position. 3174600100013 INC-SPECT No contribution from epithermal neutrons, 3174600100014 SAMPLE Natural GdB6 (~10 mg, nominal thickness of 0.1 g/cm2), 3174600100015 located ~35 m downstream from the reactor. 3174600100016 DETECTOR (HPGE,BGO) 25% relative efficiency HPGe detector and 3174600100017 BGO detector shielded by lead (10 cm thick) 3174600100018 ANALYSIS The ratio of the spectrum averaged cross section to 3174600100019 the thermal cross section (effective g-factor) was 3174600100020 obtained by integration of the sum of single-level 3174600100021 Breit-Wigner whose resonance parameters were taken 3174600100022 from the Atlas of Neutron Resonances from 0.2 meV 3174600100023 to 50 eV. 3174600100024 After considering neutron self-sheilding and gamma 3174600100025 attenuation, the effective g-factors are 3174600100026 0.887+/-0.016 for the 155Gd 88.97 keV gamma line, 3174600100027 0.859+/-0.016 for the 157Gd 79.51 keV gamma line. 3174600100028 MONITOR (5-B-10(N,A)3-LI-7,PAR,SIG,G,A) 3174600100029 MONIT-REF (31558005,Zs.Revay+,J,RCA,91,361,2003) 3174600100030 ERR-ANALYS (DATA-ERR) The uncertainty is propagated from 3174600100031 * uncertainty in the effective g-factor, 3174600100032 * uncertainty in the gamma production cross section: 3174600100033 - counting statistics 3174600100034 - gamma detection efficiency 3174600100035 - normalization by 10B(n,a) cross section. 3174600100036 etc. 3174600100037 The uncertainfy in the effective g-factor was obtained 3174600100038 by Monte Carlo simulation with sampling of resonance 3174600100039 parameters according to the standard normal 3174600100040 distribution. 3174600100041 The uncertainty in the internal conversion coefficient 3174600100042 is reported less than 1.4% in T.Kibedi et al. (2008) 3174600100043 and was not included in the error propagation. 3174600100044 REL-REF (N,,T.Kibedi+,J,NIM/A,589,202,2008) 3174600100045 Uncertainty in internal conversion coefficient 3174600100046 COMMENT By Hee Dong Choi (2014-09-29): 3174600100047 The first author performed this work on leave from 3174600100048 Seoul National University. 3174600100049 STATUS (APRVD) Proof-read by Hee Dong Choi (2014-09-29) 3174600100050 HISTORY (20140924C) On 3174600100051 ENDBIB 49 0 3174600100052 COMMON 3 3 3174600100053 E-NRM MONIT MONIT-ERR 3174600100054 KEV B B 3174600100055 478. 713. 5. 3174600100056 ENDCOMMON 3 0 3174600100057 ENDSUBENT 56 0 3174600199999 SUBENT 31746002 20140924 31663174600200001 BIB 4 7 3174600200002 REACTION (64-GD-155(N,G)64-GD-156,PAR,SIG) 3174600200003 gamma production for transition to the ground state 3174600200004 SAMPLE (64-GD-155,NAT=0.1480) 14.80+/-0.12% 3174600200005 (5-B-10,NAT=0.199) 19.9+/-0.7% 3174600200006 MISC-COL (MISC1) Effective g-factor 3174600200007 (MISC2) Internal conversion coefficient 3174600200008 STATUS (TABLE) Table II of Nucl.Sci.Eng.177(2014)219 3174600200009 ENDBIB 7 0 3174600200010 COMMON 2 3 3174600200011 EN-DUMMY LVL-FIN 3174600200012 EV MEV 3174600200013 0.0253 0. 3174600200014 ENDCOMMON 3 0 3174600200015 DATA 7 6 3174600200016 E E-ERR DATA DATA-ERR MISC1 MISC1-ERR 3174600200017 MISC2 3174600200018 KEV KEV B B NO-DIM NO-DIM 3174600200019 NO-DIM 3174600200020 88.9701 0.0010 8720. 320. 0.8873 0.0160 3174600200021 3.72 3174600200022 1129.419 0.009 1190. 190. 0.8957 0.0160 3174600200023 0.00216 3174600200024 1154.19 0.13 3100. 170. 0.8957 0.0160 3174600200025 0.00207 3174600200026 1242.482 0.010 1090. 130. 0.8957 0.0160 3174600200027 0.00077 3174600200028 1258.087 0.014 230. 16. 0.8957 0.0160 3174600200029 0.00174 3174600200030 1366.479 0.011 600. 120. 0.8957 0.0160 3174600200031 0.00065 3174600200032 ENDDATA 16 0 3174600200033 ENDSUBENT 32 0 3174600299999 SUBENT 31746003 20140924 31663174600300001 BIB 4 7 3174600300002 REACTION (64-GD-157(N,G)64-GD-158,PAR,SIG) 3174600300003 gamma production for transition to the ground state 3174600300004 SAMPLE (64-GD-157,NAT=0.1565) 15.65+/-0.02% 3174600300005 (5-B-10,NAT=0.199) 19.9+/-0.7% 3174600300006 MISC-COL (MISC1) Effective g-factor 3174600300007 (MISC2) Internal conversion coefficient 3174600300008 STATUS (TABLE) Table II of Nucl.Sci.Eng.177(2014)219 3174600300009 ENDBIB 7 0 3174600300010 COMMON 2 3 3174600300011 EN-DUMMY LVL-FIN 3174600300012 EV MEV 3174600300013 0.0253 0. 3174600300014 ENDCOMMON 3 0 3174600300015 DATA 8 6 3174600300016 E E-ERR DATA DATA-ERR MISC1 MISC1-ERR 3174600300017 MISC2 MISC2-ERR 3174600300018 KEV KEV B B NO-DIM NO-DIM 3174600300019 NO-DIM NO-DIM 3174600300020 79.510 0.010 2.47 E+04 0.05 E+04 0.8589 0.0160 3174600300021 5.88 0.09 3174600300022 977.22 0.05 8.27 E+03 0.18 E+03 0.8697 0.0160 3174600300023 0.00119 3174600300024 1186.75 0.05 9.15 E+03 0.75 E+03 0.8697 0.0160 3174600300025 0.00195 3174600300026 1259.91 0.05 2500. 190. 0.8697 0.0160 3174600300027 0.00174 3174600300028 1263.73 0.05 3690. 290. 0.8698 0.0160 3174600300029 0.00075 3174600300030 1517.57 0.07 1280. 120. 0.8698 0.0160 3174600300031 0.0011 3174600300032 ENDDATA 16 0 3174600300033 ENDSUBENT 32 0 3174600399999 SUBENT 31746004 20140924 31663174600400001 BIB 3 7 3174600400002 REACTION (64-GD-155(N,G)64-GD-156,PAR,SIG,,MSC) 3174600400003 transition cross section for (Ex<1366.526 keV)->g.s. 3174600400004 CORRECTION Measured gamma production cross section was corrected 3174600400005 for the effective g-factor and internal conversion 3174600400006 coefficients 3174600400007 STATUS (TABLE) Table II of Nucl.Sci.Eng.177(2014)219 3174600400008 (DEP,31746002) gamma production cross section 3174600400009 ENDBIB 7 0 3174600400010 NOCOMMON 0 0 3174600400011 DATA 5 1 3174600400012 EN E-MAX E-LVL-FIN DATA DATA-ERR 3174600400013 EV KEV KEV B B 3174600400014 0.0253 1366.526 0. 53300. 1900. 3174600400015 ENDDATA 3 0 3174600400016 ENDSUBENT 15 0 3174600499999 SUBENT 31746005 20140924 31663174600500001 BIB 3 7 3174600500002 REACTION (64-GD-157(N,G)64-GD-158,PAR,SIG,,MSC) 3174600500003 transition cross section for (Ex<1517.57 keV)->g.s. 3174600500004 CORRECTION Measured gamma production cross section was corrected 3174600500005 for the effective g-factor and internal conversion 3174600500006 coefficients 3174600500007 STATUS (TABLE) Table II of Nucl.Sci.Eng.177(2014)219 3174600500008 (DEP,31746003) gamma production cross section 3174600500009 ENDBIB 7 0 3174600500010 NOCOMMON 0 0 3174600500011 DATA 5 1 3174600500012 EN E-MAX E-LVL-FIN DATA DATA-ERR 3174600500013 EV KEV KEV B B 3174600500014 0.0253 1517.57 0. 226500. 5500. 3174600500015 ENDDATA 3 0 3174600500016 ENDSUBENT 15 0 3174600599999 SUBENT 31746006 20140924 31663174600600001 BIB 4 11 3174600600002 REACTION (64-GD-155(N,G)64-GD-156,,SIG,,,DERIV) 3174600600003 ANALYSIS Measured ground state transition cross section 3174600600004 complemented by the ground state transition 3174600600005 cross section from the level higher than 3174600600006 1366.526 keV calculated by DICEBOX Monte Carlo 3174600600007 simulation code 3174600600008 REL-REF (D,V1002241,S.F.Mughabghab,B,NEUT.RES,,2006) 3174600600009 60900+/-500 b 3174600600010 STATUS (TABLE) Text of Nucl.Sci.Eng.177(2014)219 3174600600011 (DEP,31746004) transition cross section for 3174600600012 (Ex<1366.526 keV)->g.s. 3174600600013 ENDBIB 11 0 3174600600014 NOCOMMON 0 0 3174600600015 DATA 3 1 3174600600016 EN DATA DATA-ERR 3174600600017 EV B B 3174600600018 0.0253 56700. 2100. 3174600600019 ENDDATA 3 0 3174600600020 ENDSUBENT 19 0 3174600699999 SUBENT 31746007 20140924 31663174600700001 BIB 4 11 3174600700002 REACTION (64-GD-157(N,G)64-GD-158,,SIG,,,DERIV) 3174600700003 ANALYSIS Measured ground state transition cross section 3174600700004 complemented by the ground state transition 3174600700005 cross section from the level higher than 3174600700006 1517.57 keV calculated by DICEBOX Monte Carlo 3174600700007 simulation code 3174600700008 REL-REF (D,V1002248,S.F.Mughabghab,B,NEUT.RES,,2006) 3174600700009 254000+/-815 b 3174600700010 STATUS (TABLE) Text of Nucl.Sci.Eng.177(2014)219 3174600700011 (DEP,31746005) transition cross section for 3174600700012 (Ex<1517.57 keV)->g.s. 3174600700013 ENDBIB 11 0 3174600700014 NOCOMMON 0 0 3174600700015 DATA 3 1 3174600700016 EN DATA DATA-ERR 3174600700017 EV B B 3174600700018 0.0253 239000. 6000. 3174600700019 ENDDATA 3 0 3174600700020 ENDSUBENT 19 0 3174600799999 ENDENTRY 7 0 3174699999999