ENTRY 31868 20250409 32193186800000001 SUBENT 31868001 20250409 32193186800100001 BIB 11 19 3186800100002 TITLE Neutron capture cross section measurement for the 3186800100003 139La(n,g)140La reaction at 0.0372 eV 3186800100004 AUTHOR (N.Belouadah, N.Osmani, K.Boukeffoussa, F.Kadem, 3186800100005 L.Yettou, M.Belgaid, N.Taibouni, M.Trari) 3186800100006 INSTITUTE (3ALGUHB,3ALGRNB,3ALGCDT) 3186800100007 REFERENCE (J,RCA,113,1,2025) 3186800100008 FACILITY (REAC,3ALGRNB) Es-Salam Research Reactor 3186800100009 SAMPLE . La2O3 (99% pure, 12 cm in diameter, 0.65 g) 3186800100010 . Au (99% purity, 25 um thick, 10 mm in diameter) 3186800100011 METHOD (DIFFR) Pb(200) single crystal 3186800100012 (ACTIV) irradiated for 8 h 3186800100013 DETECTOR (HPGE) calibrated with the standard point sources 3186800100014 (241Am, 13Ba, 60Co, 137Cs, 152Eu). 3186800100015 Resolution of 1.8 keV for 1332.5 keV gamma-rays, and 3186800100016 of 0.89 keV for 122 keV gammas-rays. 3186800100017 CORRECTION Corrected for gamma-ray attenuation 3186800100018 STATUS (TABLE,,N.Belouadah+,J,RCA,113,1,2025) Table 3 3186800100019 (APRVD) Approved by Naima Belouadah (2025-04-09) 3186800100020 HISTORY (20250409C) On 3186800100021 ENDBIB 19 0 3186800100022 NOCOMMON 0 0 3186800100023 ENDSUBENT 22 0 3186800199999 SUBENT 31868002 20250409 32193186800200001 BIB 7 18 3186800200002 REACTION (57-LA-139(N,G)57-LA-140,,SIG) 3186800200003 SAMPLE (57-LA-139,ENR=0.9991) 3186800200004 DECAY-DATA (57-LA-140,1.678D,DG,328.76,0.2030, 3186800200005 DG,487.02,0.4550, 3186800200006 DG,815.77,0.2328, 3186800200007 DG,1596.21,0.9540) 3186800200008 MONITOR (79-AU-197(N,G)79-AU-198,,SIG) 3186800200009 DECAY-MON (79-AU-198-G,2.695D,DG,411.80,0.9550) 3186800200010 ERR-ANALYS (ERR-T) Total uncertainty (5%) 3186800200011 (ERR-S) Statistical uncertainty (1%) 3186800200012 (ERR-1) Decay branching ratio (0.6%) 3186800200013 (ERR-2) Efficiency calibration (3%) 3186800200014 (ERR-3) Sapmle mass (0.01%) 3186800200015 (ERR-4) Self-shielding factor (0.01%) 3186800200016 (ERR-5) Neutron flux including Au cross section (4%) 3186800200017 COMMENT By Naima Belouadah (2025-05-05): 3186800200018 The neutron flux uncertainty (4%) includes the 3186800200019 uncertainty due to the monitor cross section (+/-2 b). 3186800200020 ENDBIB 18 0 3186800200021 COMMON 5 3 3186800200022 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 3186800200023 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3186800200024 0.6 3. 0.01 0.01 4. 3186800200025 ENDCOMMON 3 0 3186800200026 DATA 5 1 3186800200027 EN DATA ERR-T ERR-S MONIT 3186800200028 EV B B PER-CENT B 3186800200029 0.0372 7.50 0.37 1. 81.45 3186800200030 ENDDATA 3 0 3186800200031 ENDSUBENT 30 0 3186800299999 ENDENTRY 2 0 3186899999999