ENTRY 23289 20180905 22712328900000001 SUBENT 23289001 20180905 22712328900100001 BIB 13 35 2328900100002 TITLE Investigation of the 241Am(n,2n)240Am cross section 2328900100003 AUTHOR (A.Kalamara, R.Vlastou, M.Kokkoris, M.Diakaki, 2328900100004 A.Tsinganis, N.Patronis, M.Axiotis, A.Lagoyannis) 2328900100005 INSTITUTE (2GRCTUA,2GRCIOA,2GRCATH) 2328900100006 REFERENCE (J,PR/C,93,014610,2016) 2328900100007 #doi:10.1103/PhysRevC.93.014610 2328900100008 (J,NDS,119,76,2014) 2328900100009 #doi:10.1016/j.nds.2014.08.023 2328900100010 Data at 10.4 and 10.8 MeV given. 2328900100011 FACILITY (VDGT,2GRCATH) 5.5 MV VdG Tandem T11/25 accelerator 2328900100012 INC-SOURCE (D-D) En=10.0, 10.4, 10.8 MeV. Deuterium gas (130 kPa) 2328900100013 in a stainless steel gas cell (1 cm diam., 3.7 cm 2328900100014 length, 5-um-thick Mo window 2328900100015 (D-T) En=17.1 MeV. TiT target (2.1 mg/cm2) on Cu 2328900100016 backing (1 mm thick) 2328900100017 METHOD (ACTIV) Irradiated by 1-3 uA for 3 days on average. 2328900100018 SAMPLE Two AmO2 targets (IRMM2 & IRMM3, ~5 GBq) pressed into 2328900100019 pellets with Al2O3 and encapsulated into Al containers2328900100020 (Same batch of targets used by Sage's experiment.) 2328900100021 - IRMM2: 42 mg Am irradiated at En=10.8 MeV 2328900100022 - IRMM3: 40 mg Am irradiated at En=10.0,10.4,17.1 MeV 2328900100023 The Au and Nb foils irradiated together to monitor 2328900100024 neutron flux: Al(front)/Am/Al(back)/Au/Nb 2328900100025 DETECTOR (HPGE) Four HPGe detectors calibrated by a 152Eu 2328900100026 source (relative efficiency of 100%,80%,56% and 16%) 2328900100027 (BF3) Neutron monitor at 3 m away from the neutron 2328900100028 source 2328900100029 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 2328900100030 DECAY-MON (11-NA-24,14.96HR,DG,1368.6,1.) 2328900100031 STATUS (APRVD) Approved by Rosa Vlastou (2017-02-27) 2328900100032 HISTORY (20160225C) M.M. 2328900100033 (20170210A) On. 002+003 deleted (as per a comment from 2328900100034 Rosa Vlastou (2017-02-03). 2328900100035 (20180905U) VS. Ref. Nucl.Data Sheets 119(2014)76 2328900100036 and monitor added. 2328900100037 ENDBIB 35 0 2328900100038 NOCOMMON 0 0 2328900100039 ENDSUBENT 38 0 2328900199999 NOSUBENT 23289002 20170210 22582328900200001 NOSUBENT 23289003 20170210 22582328900300001 SUBENT 23289004 20170210 22582328900400001 BIB 7 18 2328900400002 REACTION (95-AM-241(N,2N)95-AM-240,,SIG) 2328900400003 DECAY-DATA (95-AM-240,50.8HR,DG,987.8,0.732) 2328900400004 ANALYSIS Two methods (experimental and MCNP simulation) were 2328900400005 applied for determination of the counting efficiency 2328900400006 and self-absorption, and the weighted-average of two 2328900400007 results was considered as the final result. 2328900400008 Neutron fluence determined by MCNP simulation was 2328900400009 adopted in the cross section determination. 2328900400010 MISC-COL (MISC1) Cross sections corrected for counting 2328900400011 efficiency and self-absorption experimentally 2328900400012 (MISC2) Cross sections corrected for counting 2328900400013 efficiency and self-absorption by MCNP simulation 2328900400014 ERR-ANALYS (ERR-T) Total uncertainty 2328900400015 (ERR-1,1.,2.) Neutron energy (1-2%) 2328900400016 (ERR-2) Neutron integrated flux (5%) 2328900400017 (ERR-3,3.,4.) Detector efficiency (3-4%) 2328900400018 STATUS (TABLE) Table IV of Phys.Rev.C93(2016)014610 2328900400019 HISTORY (20160210A) On. ERR-ANALYS updated. MISC1/2 added. 2328900400020 ENDBIB 18 0 2328900400021 COMMON 1 3 2328900400022 ERR-2 2328900400023 PER-CENT 2328900400024 5. 2328900400025 ENDCOMMON 3 0 2328900400026 DATA 8 4 2328900400027 EN EN-RSL DATA ERR-T MISC1 MISC1-ERR 2328900400028 MISC2 MISC2-ERR 2328900400029 MEV MEV MB MB MB MB 2328900400030 MB MB 2328900400031 10.0 0.1 203. 15. 213. 18. 2328900400032 182. 28. 2328900400033 10.4 0.1 229. 16. 231. 21. 2328900400034 227. 23. 2328900400035 10.8 0.1 237. 20. 237. 22. 2328900400036 238. 43. 2328900400037 17.1 0.3 135. 11. 134. 11. 2328900400038 142. 27. 2328900400039 ENDDATA 12 0 2328900400040 ENDSUBENT 39 0 2328900499999 ENDENTRY 4 0 2328999999999