ENTRY 31830 20220309 32073183000000001 SUBENT 31830001 20220309 32073183000100001 BIB 10 24 3183000100002 TITLE Measurement of the thermal neutron capture cross 3183000100003 section by 9Be using the neutron flux from a nuclear 3183000100004 research reactor and the AMS technique 3183000100005 AUTHOR (D.J.Marin-Lambarri, J.Garcia-Ramirez, 3183000100006 E.Sanchez-Zuniga, S.Padilla, L.Acosta, E.Chavez, 3183000100007 H.S.Cruz-Galindo, A.Huerta, G.Mendez, 3183000100008 R.Raya-Arredondo, M.Rodriguez-Ceja, C.Solis, 3183000100009 L.Barron-Palos) 3183000100010 INSTITUTE (3MEXUMX,3MEXINI) 3183000100011 REFERENCE (J,PR/C,102,044601,2020) 3183000100012 ANALYSIS By Daniel Jose Martin-Lambarri (2020-10-21): 3183000100013 The neutron flux is measured rutinely by the TRIGA 3183000100014 Mark III engineers with the Au foil activation method,3183000100015 and it was the flux value we used. 3183000100016 FACILITY (REAC,3MEXINI) 1 MW TRIGA MARK III reactor 3183000100017 ADD-RES The 13C(n,g)14C thermal cross section measured by 3183000100018 graphite irradiation and AMS was 0.18+/-0.03 b, 3183000100019 which is biased by the 14C originated from the 14N 3183000100020 impurities (~1%) in the graphite sample through the 3183000100021 14N(n,p)14C reaction. 3183000100022 ERR-ANALYS (DATA-ERR) No information on the source of uncertainty 3183000100023 STATUS (TABLE) Text (p.044601-4) of Phys.Rev.C.102(2020)0446013183000100024 HISTORY (20201016C) On 3183000100025 (20220309A) On. Major revision in 003. 3183000100026 ENDBIB 24 0 3183000100027 NOCOMMON 0 0 3183000100028 ENDSUBENT 27 0 3183000199999 SUBENT 31830002 20201016 31983183000200001 BIB 4 8 3183000200002 REACTION (4-BE-9(N,G)4-BE-10,,SIG,,SPA) 3183000200003 SAMPLE BeO (approx. 8 mg of Be each) prepared from 8 ml of Be 3183000200004 standard solution 3183000200005 INC-SOURCE (REAC) SIRCA station (2.6E+12 thermal neutrons/cm2/s 3183000200006 and 2.26E+11 epithermal neutrons/cm2/s) 3183000200007 METHOD (ACTIV) Three samples (B1,B2,B3) were irradiated for 3183000200008 1800, 7200 and 1800 sec, respectively. 3183000200009 (AMS) 01-5-1 standard sample used 3183000200010 ENDBIB 8 0 3183000200011 NOCOMMON 0 0 3183000200012 DATA 3 1 3183000200013 EN-DUMMY DATA DATA-ERR 3183000200014 EV B B 3183000200015 0.0253 9.7 0.53 3183000200016 ENDDATA 3 0 3183000200017 ENDSUBENT 16 0 3183000299999 SUBENT 31830003 20220309 32073183000300001 BIB 5 7 3183000300002 REACTION (7-N-14(N,P)6-C-14,,SIG,,SPA) 3183000300003 SAMPLE Uracil (C4H4N2O2) 3183000300004 INC-SOURCE (REAC) SINCA station (4.42E+12 thermal neutrons/cm2/s) 3183000300005 METHOD (ACTIV) Two samples (U1 and U2) were irradiated for 3183000300006 20 sec. 3183000300007 (AMS) 3183000300008 HISTORY (20220309A) On. REACTION(SF3-SF4) corrected. 3183000300009 ENDBIB 7 0 3183000300010 NOCOMMON 0 0 3183000300011 DATA 3 1 3183000300012 EN-DUMMY DATA DATA-ERR 3183000300013 EV B B 3183000300014 0.0253 2.07 0.37 3183000300015 ENDDATA 3 0 3183000300016 ENDSUBENT 15 0 3183000399999 ENDENTRY 3 0 3183099999999