ENTRY 32217 20200907 31973221700000001 SUBENT 32217001 20200907 31973221700100001 BIB 13 80 3221700100002 TITLE Measurements of neutron capture cross-section for 3221700100003 tantalum at the neutron filtered beams 3221700100004 AUTHOR (O.Gritzay, V.Libman) 3221700100005 INSTITUTE (4UKRIJD) 3221700100006 REFERENCE (C,2008AKERSL,,549,2008) All results presented 3221700100007 (C,2008KYIV,,548,2008) first result at 59 keV 3221700100008 (C,2006KYIV,,569,2006) first result at 2 keV 3221700100009 (W,GRITZAY,20110318) Data with revised uncertainties 3221700100010 FACILITY (REAC,4UKRIJD) Reactor WWR-M 3221700100011 INC-SOURCE (REAC) Neutron filters installed in horizontal channel 3221700100012 of the reactor. 3221700100013 METHOD (FNB,ACTIV) Activation of tantalic samples was done 3221700100014 during 84 hours for 2 keV and 62 + 84 hours for 59 keV,3221700100015 then the targets were removed to the clean zone for the3221700100016 further measurements. 3221700100017 DETECTOR (GELI)Detector type - DGDK-45A; energy resolution - 3221700100018 3.4 keV at 1332 keV gamma-line; lead shield with 15 cm 3221700100019 thickness. 3221700100020 (SPEC,GELI) Spectrometer with two Ge(Li) detectors 3221700100021 DGDK-32B was placed at the horizontal channel and used 3221700100022 to determine the incident neutron flux. 3221700100023 The spectrometer was calibrated on energy and 3221700100024 efficiency using the sources 133Ba and 152Eu from the 3221700100025 SOSGI-M standard set. The value of the absolute 3221700100026 efficiency of registration for gamma-line 478 keV from 3221700100027 reaction 10B(n,alpha+gamma) was (3.08+-0.17)*10-5. 3221700100028 (HE3SP)Exposing the tantalic targets, simultaneously 3221700100029 the monitoring of the neutron flux has been done by the3221700100030 neutron spectrometer with 3He-counter. The measurements3221700100031 of the neutron beam have been done every 1000 s after 3221700100032 each 2600 s of the total exposition. 3221700100033 SAMPLE (73-TA-181,ENR=0.99988) The tantalic targets were made 3221700100034 of natural tantalum foil and the targets had the 3221700100035 28.0 mm diameter. 3221700100036 (5-B-10,ENR=0.85) The boron target used to define the 3221700100037 neutron flux value, was made of the boric powder, 3221700100038 enriched by 10B. This target is placed inside the 3221700100039 container with 28 mm diameter. The thickness of the 3221700100040 boron target was 1 mm, weight = 0.6732 g. 3221700100041 DECAY-DATA The following nine gamma lines were used for 3221700100042 determination of the sample activities: 3221700100043 (73-TA-182-G,114.74D,DG,152.43,0.0693, 3221700100044 DG,179.39,0.0308, 3221700100045 DG,222.1096,0.0749, 3221700100046 DG,229.322,0.0363, 3221700100047 DG,264.0752,0.036, 3221700100048 DG,1121.3008,0.349, 3221700100049 DG,1189.05,0.1623, 3221700100050 DG,1221.41,0.2698, 3221700100051 DG,1231.0157,0.1144) 3221700100052 CORRECTION Correction on the resonance self-shielding of neutrons 3221700100053 in the tantalic samples was done. The real values of 3221700100054 cross-sections were received by extrapolation the 3221700100055 observed cross sections to zero thickness of the 3221700100056 samples. 3221700100057 To estimate a share of cross-section from the impure 3221700100058 lines, a numerical simulation was performed. 3221700100059 Corrections for backward scattering of neutrons by the 3221700100060 output collimator were computed with program package 3221700100061 MCNP-4C for real irradiation conditions. 3221700100062 MONITOR (5-B-10(N,A)3-LI-7,PAR,SIG,G) The neutron flux was 3221700100063 defined by area of the full absorption peak of gamma 3221700100064 rays with 478 keV energy (the excited state of 7Li). 3221700100065 Cross sections of the 10B(n,alpha+gamma)7Li* reaction 3221700100066 were calculated as mean values of the averaged on a 3221700100067 filtered neutron beam shape of the point-wise cross 3221700100068 sections, taken from CENDL-2, ENDF/B-VI, JENDL-3.3 and 3221700100069 JEF-3.0. 3221700100070 HISTORY (20080829C) UKRNDC 3221700100071 (20101208C) OG: Conference codes and two co-authors 3221700100072 were added. 3221700100073 (20110318A) ERR-ANALYS modified and moved to subentries3221700100074 Data for 2 keV and 59 keV are presented in separate 3221700100075 subentries. 3221700100076 (20141212U) VS. BIB minor corrections. 3221700100077 (20171228U) On. REFERENCE: C,2008AKERSL added. 3221700100078 (20200527A) OG. Replacement of AV by SPA. STATUS added 3221700100079 in Sub002-003. EN-MIN, EN-MAX updated. INC-SPECT from 3221700100080 Sub001-> in Sub002, 003 and updated. 3221700100081 (20200907A) OG. MONITOR added. SAMPLE updated. 3221700100082 ENDBIB 80 0 3221700100083 NOCOMMON 0 0 3221700100084 ENDSUBENT 83 0 3221700199999 SUBENT 32217002 20200907 31973221700200001 BIB 6 37 3221700200002 REACTION (73-TA-181(N,G)73-TA-182,,SIG,,SPA) 3221700200003 SAMPLE A pile of four 0.2 mm thickness tantalic targets was 3221700200004 used. 3221700200005 ERR-ANALYS (ERR-T) Absolute uncertainty of cross section- 3221700200006 it includes the uncertainties of- 3221700200007 (ERR-1) Error in extrapolated cross-section - it 3221700200008 includes the uncertainties of- 3221700200009 error in determination of sample activities 1.7-4.4% 3221700200010 statistical error in peak area 1.0-5.0% 3221700200011 error in gamma-line efficiency 4.2% 3221700200012 (ERR-2) Error in determination of Ta sample mass 0.011%3221700200013 (ERR-3) Error in determination of neutron flux - it 3221700200014 includes the uncertainties of- 3221700200015 error in determination of B sample mass 0.024% 3221700200016 error in the B gamma-line efficiency 2.04% 3221700200017 error in quantum yield gamma-lines 0.05-0.48 3221700200018 error in cross section of the 10-B(n,alpha+gamma)7-Li 3221700200019 reaction 0.50% 3221700200020 (ERR-4) Error due to the impure lines in filtered beam 3221700200021 (ERR-5) Error due to backward scattering of neutrons by3221700200022 the output collimator 0.3% 3221700200023 INC-SPECT Filter 2 keV. Average energy of filtered neutron 3221700200024 (1.795 (+0.645,-0.724))keV (95% response function), 3221700200025 the filter components (g/cm2): 3221700200026 Sc-167.6, Ti-10.89, Co-13.07, 10B(85%)-0.2. 3221700200027 Purity of beam about 95.73%, main parasitic lines: 3221700200028 35 keV - 0.35%, 43 keV - 0.55%, 49 keV - 1.23%. 3221700200029 Neutron flux was 8.9e+06 n/cm2/s. Time of irradiation 3221700200030 was 302400 s. 3221700200031 STATUS (TABLE) Private communication with Gritzay (2011) 3221700200032 (SUPPL,32216003) Neutron spectrum after filter 2 keV 3221700200033 HISTORY (20141212U) VS. DECAY-DATA moved to subent. 001. and 3221700200034 DG added. 3221700200035 (20200527A) OG. Replacement of AV by SPA. STATUS and 3221700200036 INC-SPECT added. EN-MIN, EN-MAX updated. 3221700200037 (20200907A) OG. MONIT and SAMPLE added. 3221700200038 (20201203A) On. E-NRM=478 keV added. 3221700200039 ENDBIB 37 0 3221700200040 COMMON 5 3 3221700200041 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 3221700200042 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3221700200043 4.70 0.011 2.10 3.8 0.3 3221700200044 ENDCOMMON 3 0 3221700200045 DATA 6 1 3221700200046 EN-MIN EN-MAX DATA ERR-T E-NRM MONIT 3221700200047 KEV KEV B B KEV B 3221700200048 0.466 2.903 6.54 0.42 478. 13.61 3221700200049 ENDDATA 3 0 3221700200050 ENDSUBENT 49 0 3221700299999 SUBENT 32217003 20200907 31973221700300001 BIB 6 37 3221700300002 REACTION (73-TA-181(N,G)73-TA-182,,SIG,,SPA) 3221700300003 SAMPLE A pile of eight 0.1 mm thickness tantalic targets was 3221700300004 used. 3221700300005 ERR-ANALYS (ERR-T) Absolute uncertainty of cross section- 3221700300006 it includes the uncertainties of- 3221700300007 (ERR-1) Error in extrapolated cross-section - it 3221700300008 includes the uncertainties of- 3221700300009 error in determination of sample activities 1.3-4.4% 3221700300010 statistical error in peak area 1.2-21.1% 3221700300011 error in gamma-line efficiency 4.2% 3221700300012 error in quantum yield gamma-lines 0.05-0.48 3221700300013 (ERR-2) Error in determination of Ta sample mass 0.057%3221700300014 (ERR-3) Error in determination of neutron flux - it 3221700300015 includes the uncertainties of- 3221700300016 error in determination of B sample mass 0.024% 3221700300017 error in the B gamma-line efficiency 2.04% 3221700300018 error in cross section of the 10-B(n,alpha+gamma)7-Li 3221700300019 reaction 1.29% 3221700300020 (ERR-4) Error due to the impure lines in filtered beam 3221700300021 (ERR-5) Error due to backward scattering of neutrons by3221700300022 the output collimator 3.7% 3221700300023 INC-SPECT Filter 59 keV. Average energy of filtered neutron 3221700300024 (58.424 (+1.929,-4.535)) keV (95% response function), 3221700300025 the filter components (g/cm2): 58Ni - 84.55, S - 157.7,3221700300026 V - 17.4, Pb - 2.5, Al - 5.4, 10B - 0.2. The purity of3221700300027 beam was about 97.0%, main parasitic lines: 3221700300028 368 keV - 0.62%, 690 keV - 1.29%. 3221700300029 Neutron flux was 2.62e+06 n/cm2/s. Total time of 3221700300030 irradiation was 527040 s. 3221700300031 STATUS (TABLE) Private communication with Gritzay (2011) 3221700300032 (SUPPL,32214004) Neutron spectrum after filter 59 keV 3221700300033 HISTORY (20141212U) VS. DECAY-DATA moved to subent. 001 and 3221700300034 DG added. 3221700300035 (20200527A) OG. Replacement of AV by SPA. STATUS and 3221700300036 INC-SPECT added. EN-MIN, EN-MAX updated. 3221700300037 (20200907A) OG. MONIT and SAMPLE added. 3221700300038 (20201203A) On. E-NRM=478 keV added. 3221700300039 ENDBIB 37 0 3221700300040 COMMON 5 3 3221700300041 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 3221700300042 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3221700300043 4.58 0.057 4.48 3.2 3.7 3221700300044 ENDCOMMON 3 0 3221700300045 DATA 6 1 3221700300046 EN-MIN EN-MAX DATA ERR-T E-NRM MONIT 3221700300047 KEV KEV B B KEV B 3221700300048 33.403 60.125 0.480 0.039 478. 2.35 3221700300049 ENDDATA 3 0 3221700300050 ENDSUBENT 49 0 3221700399999 ENDENTRY 3 0 3221799999999