ENTRY 14794 20240403 1479400000001 SUBENT 14794001 20240403 20240513 1479400100001 BIB 10 31 1479400100002 TITLE Unifying measurement of 239Pu(n,g) in the keV to MeV 1479400100003 energy regime 1479400100004 AUTHOR (S.Mosby,T.A.Bredeweg,A.Couture,M.Jandel,T.Kawano, 1479400100005 J.L.Ullmann,R.A.Henderson,C.Y.Wu) 1479400100006 INSTITUTE (1USALAS,1USALRL) 1479400100007 REFERENCE (J,PR/C,97,041601,2018) 1479400100008 #doi:10.1103/PhysRevC.97.041601 1479400100009 (J,NDS,148,312,2018) 1479400100010 #doi:10.1016/j.nds.2018.02.007 1479400100011 FACILITY (LINAC,1USALAS) Experiment performed at the the Manuel 1479400100012 Lujan Jr. Neutron Scattering Center at the Los Alamos 1479400100013 Neutron Science Center 1479400100014 SAMPLE Two samples of 239Pu were used. Thin sample (approx. 1479400100015 1 mg of 239Pu) was measured in a parallel plate 1479400100016 avalanche counter to measure capture cross section. 1479400100017 A second target with mass of 50 mg of 239Pu was 1479400100018 measured to achieve good statistics at higher energies.1479400100019 Scattered neutron background was measured using 208Pb 1479400100020 target with Ni foils on both sides to represent thick 1479400100021 (200 mg/cm2) cladding which surrounded the 239Pu. 1479400100022 DETECTOR (BAF2,PPAC) Gamma rays were detected using DANCE array,1479400100023 consisting of 160 BaF2 crystals covering the whole 1479400100024 4Pi solid angle. DANCE is located on the 20 m neutron 1479400100025 flight path 14. Coincidence window was set to 6 ns. 1479400100026 INC-SOURCE (SPALL) Neutrons were produced by spallation reaction 1479400100027 of 800 MeV protons on tungsten target 1479400100028 METHOD (TOF) Incident neutron energy was determined by 1479400100029 time of flight 1479400100030 HISTORY (20221008C) Compiled by S.H. 1479400100031 (20240330A) OS. DETECTOR updated, MONITOR added in 1479400100032 sub.2 1479400100033 ENDBIB 31 0 1479400100034 NOCOMMON 0 0 1479400100035 ENDSUBENT 34 0 1479400199999 SUBENT 14794002 20240403 20240513 1479400200001 BIB 5 8 1479400200002 REACTION (94-PU-239(N,G)94-PU-240,,SIG) 1479400200003 MONITOR (94-PU-239(N,ABS),,ALF) 1479400200004 ERR-ANALYS (DATA-ERR) Origin of uncertainties not described 1479400200005 At all incident neutron energies, systematic 1479400200006 uncertainty from the background subtraction is the 1479400200007 dominant source of uncertainty. 1479400200008 STATUS (TABLE,,S.Mosby+,J,NDS,148,312,2018) Table 1 1479400200009 HISTORY (20240330A) MONITOR, EN-NRM-MIN/MAX added 1479400200010 ENDBIB 8 0 1479400200011 COMMON 2 3 1479400200012 EN-NRM-MIN EN-NRM-MAX 1479400200013 EV EV 1479400200014 37. 100. 1479400200015 ENDCOMMON 3 0 1479400200016 DATA 5 61 1479400200017 EN-MIN EN-MAX DATA +DATA-ERR -DATA-ERR 1479400200018 KEV KEV B PER-CENT PER-CENT 1479400200019 1.00 1.12 4.08 3.9 3.9 1479400200020 1.12 1.26 3.53 3.9 3.9 1479400200021 1.26 1.41 3.41 3.9 3.9 1479400200022 1.41 1.58 3.93 3.9 3.9 1479400200023 1.58 1.78 4.66 3.9 3.9 1479400200024 1.78 2.00 3.95 3.9 3.9 1479400200025 2.00 2.24 3.22 3.9 3.9 1479400200026 2.24 2.51 3.15 3.9 3.9 1479400200027 2.51 2.82 2.69 3.9 3.9 1479400200028 2.82 3.16 2.86 3.9 3.9 1479400200029 3.16 3.55 2.20 3.9 3.9 1479400200030 3.55 3.98 2.09 3.9 3.9 1479400200031 3.98 4.47 2.13 3.9 3.9 1479400200032 4.47 5.01 1.83 3.9 3.9 1479400200033 5.01 5.62 1.76 3.9 3.9 1479400200034 5.62 6.31 1.75 3.9 3.9 1479400200035 6.31 7.08 1.56 3.9 3.9 1479400200036 7.08 7.94 1.31 4.0 4.0 1479400200037 7.94 8.91 1.20 4.0 4.0 1479400200038 8.91 10.0 1.06 4.0 4.0 1479400200039 10.0 11.2 1.00 4.0 4.0 1479400200040 11.2 12.5 0.93 4.0 4.0 1479400200041 12.5 14.1 0.82 4.0 4.1 1479400200042 14.1 15.8 0.77 4.1 4.2 1479400200043 15.8 17.7 0.74 4.1 4.2 1479400200044 17.7 22.3 0.66 4.1 4.3 1479400200045 22.3 25.1 0.59 4.2 4.5 1479400200046 25.1 28.1 0.51 4.2 4.6 1479400200047 28.1 31.6 0.50 4.2 4.7 1479400200048 31.6 35.4 0.48 4.6 5.1 1479400200049 35.4 39.8 0.42 5.2 5.7 1479400200050 39.8 44.6 0.40 4.6 5.3 1479400200051 44.6 50.1 0.36 4.6 5.4 1479400200052 50.1 56.2 0.34 4.7 5.7 1479400200053 56.2 63.1 0.30 4.8 5.9 1479400200054 63.1 70.7 0.29 4.9 6.1 1479400200055 70.7 79.4 0.28 4.9 6.4 1479400200056 79.4 89.1 0.28 5.5 7.1 1479400200057 100. 112. 0.24 5.5 7.7 1479400200058 112. 125. 0.23 5.7 8.2 1479400200059 125. 141. 0.22 5.7 8.7 1479400200060 141. 158. 0.21 6.6 9.7 1479400200061 158. 177. 0.206 6.6 10.2 1479400200062 177. 199. 0.201 6.6 10.9 1479400200063 199. 223. 0.189 7.0 11.9 1479400200064 223. 251. 0.174 7.3 12.8 1479400200065 251. 281. 0.159 7.6 13.9 1479400200066 281. 316. 0.156 8.1 15.2 1479400200067 316. 354. 0.133 8.6 16.7 1479400200068 354. 398. 0.131 9.2 18.3 1479400200069 398. 446. 0.126 10.0 20.2 1479400200070 446. 501. 0.113 10.8 22.3 1479400200071 501. 562. 0.099 11.7 24.7 1479400200072 562. 630. 0.094 12.6 27.3 1479400200073 630. 707. 0.078 13.7 30.3 1479400200074 707. 794. 0.081 14.7 33.4 1479400200075 794. 891. 0.053 16.8 37.5 1479400200076 891. 1000. 0.052 18.2 41.6 1479400200077 1000. 1122. 0.042 20.8 46.6 1479400200078 1122. 1258. 0.029 24.8 52.8 1479400200079 1258. 1412. 0.028 26.5 58.5 1479400200080 ENDDATA 63 0 1479400200081 ENDSUBENT 80 0 1479400299999 ENDENTRY 2 0 1479499999999