ENTRY 23606 20230628 2360600000001 SUBENT 23606001 20230628 20240316 2360600100001 BIB 16 64 2360600100002 TITLE 241Am Neutron Capture Cross Section in the keV region 2360600100003 using Si and Fe-filtered neutron beams 2360600100004 AUTHOR (G.Rovira,A.Kimura,S.Nakamura,S.Endo,O.Iwamoto, 2360600100005 N.Iwamoto,T.Katabuchi,Y.Kodama,H.Nakano) 2360600100006 INSTITUTE (2JPNJAE,2JPNTIT) 2360600100007 REFERENCE (J,NST,60,489,2023) 2360600100008 #doi:10.1080/00223131.2022.2116496 2360600100009 REL-REF (I,,K.Kino+,J,NIM/A,736,66,2014) 2360600100010 Energy resolution of the pulsed neutron. 2360600100011 (I,,G.Rovira,J,NIM/A,1003,165318,2021) 2360600100012 Experimental setup and filtered neutron spectrum. 2360600100013 FACILITY (SYNCY,2JPNJAE)ANNRI(BL04) beam line of MLF at J-PARC 2360600100014 INC-SOURCE (SPALL) Spallation reaction in a mercury target 2360600100015 irradiated with 3-GeV protons. The proton beam was 2360600100016 supplied at a repetition rate of 25 Hz and in the 2360600100017 "double-bunch mode", in which the pulsed protons 2360600100018 consist of two bunches, each with a width of 100 ns, 2360600100019 at intervals of 600 ns. To improve neutron energy 2360600100020 resolution, Fe or Si neutron filters with thickness 2360600100021 of 20 cm were installed. 2360600100022 INC-SPECT (EN-RSL) One standard deviation. 2360600100023 METHOD (FNB,TOF) Neutron TOF experiment with a neutron 2360600100024 filtering system. 2360600100025 DETECTOR (NAICR) 330 mm (diam.) and 203 mm in thickness, 90 2360600100026 deg with respect to the neutron beam line. 2360600100027 DAQ: CAEN V1720 Digitizer (12bit, 250MHz) 2360600100028 SAMPLE A pellet of 7.47(10) mg (957 MBq) of Am-241 oxide 2360600100029 enclosed in an Al casing with 46.0 mg of Y2O3 used as 2360600100030 binder was used. The pellet was shaped like a disk 2360600100031 with 10 mm in diameter and 0.5 mm in thickness. The 2360600100032 sample was encapsulated in an Al container with 0.1- 2360600100033 mm-thick walls and an outer diameter of 22.0(1) mm. 2360600100034 A dummy sample, an Al container with the identical 2360600100035 dimensions to the Am-241 sample, including only Y2O3, 2360600100036 was also used for background measurements. 2360600100037 A carbon sample with a diameter of 10 mm and a 2360600100038 thickness of 0.5 mm was used as neutron scatterer 2360600100039 to subtract background. 2360600100040 A gold sample with a 10 mm diameter, 0.1 mm thickness 2360600100041 was used for normalization. 2360600100042 A boron sample with a 90.4% B-10 enrichment and a mass 2360600100043 86.1 mg was used to deduce a neutron spectrum. 2360600100044 ANALYSIS The pulse height weighting technique (PHWT) was 2360600100045 applied to derive the neutron capture yield. 2360600100046 Measurements with the carbon sample, "Dummy sample", 2360600100047 and "Blank (no sample) " were used for background 2360600100048 estimation. A measurement with the gold sample was 2360600100049 used for the normalization. The neutron capture cross 2360600100050 section of Am-241 was determined relative to the 2360600100051 capture cross section of Au-197 at each energy point. 2360600100052 CORRECTION Dead time correction was applied with the extended 2360600100053 dead-time model. Correction factors for self 2360600100054 shielding and multiple scattering were deduced using 2360600100055 the PHITS. Contributions of discriminated gamma-rays 2360600100056 to the capture yields were estimated from theoretical 2360600100057 calculation using the nuclear reaction model code 2360600100058 CCONE and detector response functions. Correction 2360600100059 factors for fission events were deduced using the 2360600100060 capture and fission cross-sections of Am-241 in 2360600100061 JENDL-5 and the gamma-ray multiplicities for the 2360600100062 capture and fission reactions. 2360600100063 MONITOR (79-AU-197(N,G)79-AU-198,,SIG) 2360600100064 MONIT-REF (,,3,JENDL-5,,2021) 2360600100065 HISTORY (20231110C) Compiled by A. Kimura. 2360600100066 ENDBIB 64 0 2360600100067 NOCOMMON 0 0 2360600100068 ENDSUBENT 67 0 2360600199999 SUBENT 23606002 20230628 20240316 2360600200001 BIB 3 29 2360600200002 REACTION (95-AM-241(N,G)95-AM-242,,SIG) 2360600200003 ERR-ANALYS (ERR-T) Total uncertainty. 2360600200004 (ERR-1) Statistical uncertainty for the Am-241 sample 2360600200005 measurement. 2360600200006 (ERR-2) Statistical uncertainty for the Au sample 2360600200007 measurement. 2360600200008 (ERR-SYS) Total systematic uncertainty. Including 2360600200009 "MONITOR-ERR" and "ERR-3" to "ERR-9". 2360600200010 (MONIT-ERR) Systematic uncertainty related to 2360600200011 standard 197Au cross section. 2360600200012 (ERR-3) Systematic uncertainty related to the dead 2360600200013 time correction. 2360600200014 (ERR-4) Systematic uncertainty related to the self- 2360600200015 shielding, multiple scattering, and fission 2360600200016 corrections. 2360600200017 (ERR-5) Systematic uncertainty related to the 2360600200018 corrections for gamma-rays below threshold. 2360600200019 (ERR-6) Systematic uncertainty related to the 2360600200020 weighting function for the Am-241 sample measurement. 2360600200021 (ERR-7) Systematic uncertainty related to the 2360600200022 weighting function for the Au sample measurement. 2360600200023 (ERR-8) Systematic uncertainty related to the area 2360600200024 density of the Am-241 sample. 2360600200025 (ERR-9) Systematic uncertainty related to the area 2360600200026 density of the Au sample. 2360600200027 STATUS (TABLE,,G.Rovira+,J,NST,60,489,2023) Tables 4,5, and 6 2360600200028 (SUPPL,23746003) Neutron spectrum at 23.5 keV 2360600200029 (SUPPL,23746004) Neutron spectrum at 51.5 keV 2360600200030 (SUPPL,23746005) Neutron spectrum at 127.7 keV 2360600200031 ENDBIB 29 0 2360600200032 COMMON 9 6 2360600200033 ERR-SYS MONIT-ERR ERR-3 ERR-4 ERR-5 ERR-6 2360600200034 ERR-7 ERR-8 ERR-9 2360600200035 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2360600200036 PER-CENT PER-CENT PER-CENT 2360600200037 3.2 2.0 0.0 0.3 0.4 1.02360600200038 1.0 1.7 1.0 2360600200039 ENDCOMMON 6 0 2360600200040 DATA 8 3 2360600200041 EN -EN-RSL +EN-RSL DATA ERR-T ERR-1 2360600200042 ERR-2 MONIT 2360600200043 KEV KEV KEV B B PER-CENT 2360600200044 PER-CENT B 2360600200045 23.5 2.1 0.9 2.72 0.29 9.72360600200046 3.3 0.644 2360600200047 51.5 8.6 9.7 2.14 0.26 11.22360600200048 3.3 0.428 2360600200049 127.7 15.7 8.8 1.32 0.10 6.82360600200050 2.0 0.2875 2360600200051 ENDDATA 10 0 2360600200052 ENDSUBENT 51 0 2360600299999 ENDENTRY 2 0 2360699999999