ENTRY 22547 20080121 21932254700000001 SUBENT 22547001 20080121 21932254700100001 BIB 16 39 2254700100002 REFERENCE (C,94GATLIN,2,944,1994) 2254700100003 TITLE -New Measurement of activation cross section for the 2254700100004 Cu-63(n,2n)Cu-62 and Cu-64(n,2n)Cu-63 Reactions at 2254700100005 Energy Range of 13.3 to 14.9 MeV. 2254700100006 AUTHOR (Y.IKEDA,D.L.SMITH, Y.UNO,Y.KASUGAI, C.KONNO,H.MAEKAWA)2254700100007 INSTITUTE (2JPNJAE) Ikeda,Uno,Konno,Maekawa 2254700100008 (1USAAIF) Smith 2254700100009 (2JPNNAG) Kasugai 2254700100010 FACILITY JAERI FNS facility. 2254700100011 INC-SOURCE (D-T) D+ beam of 2mA and 350 keV bombarded 3T target. 2254700100012 INC-SPECT Neutron flux at sample was monitored with Al foils. 2254700100013 SAMPLE 1. Natural copper samples of 10mm diameter and 0.2mm 2254700100014 thick were deployed at 100mm radius at angles of 0.deg2254700100015 to 165.deg to incident d+ beam. 2254700100016 2. Pneumatic sample transfer system was used. Eight 2254700100017 tubes were set around d-t source from 0deg to 165deg. 2254700100018 METHOD (ACTIV) 1.Irradiation time 3 m.Each sample was measured2254700100019 at least three times at different cooling times. 2254700100020 2.Irradiation and cooling time was 1min,and 2 to 3 min2254700100021 respectively. 2254700100022 RAD-DET (29-CU-62,AR) Annihilation gamma-rays from Cu samples, 2254700100023 encapsuled in 0.8mm thick lead, were counting by 2254700100024 Ge detector immediately after irradiation. 2254700100025 DETECTOR (GELI) 2254700100026 MONITOR (13-AL-27(N,P)12-MG-27,,SIG) 2254700100027 ((MONIT)41-NB-93(N,2N)41-NB-92-M,,SIG) 2254700100028 Al-27(n,p) reaction cross-section was calibrated by 2254700100029 Nb-93(n,2n)Nb-92m reaction cross-section from 2254700100030 MONIT-REF 2254700100031 MONIT-REF (22312006,Y.Ikeda+,J,NST,30,(9),26,1993) 2254700100032 CORRECTION Corrections were applied for count loss due to 2254700100033 Summation of cascade gammas, self absorption in the 2254700100034 Samples, fluctuation of the neutron flux during 2254700100035 Irradiation, and for contribution of low energy 2254700100036 Neutrons to the reaction rate. 2254700100037 ERR-ANALYS (DATA-ERR) Errors are not specified. 2254700100038 HISTORY (20070724C) M.M./S.M. 2254700100039 (20080121A) M.M. DATA units were corrected: MB -> B 2254700100040 in according to units, given in Fig.4 and 5. 2254700100041 ENDBIB 39 0 2254700100042 COMMON 2 3 2254700100043 MONIT MONIT-ERR 2254700100044 MB MB 2254700100045 459. 15. 2254700100046 ENDCOMMON 3 0 2254700100047 ENDSUBENT 46 0 2254700199999 SUBENT 22547002 20080121 21932254700200001 BIB 4 7 2254700200002 REACTION (29-CU-63(N,2N)29-CU-62,,SIG) 2254700200003 Cross section measured by 1st METHOD. 2254700200004 DECAY-DATA (29-CU-62,9.74MIN,DG,511.) 2254700200005 STATUS (PRELM) 2254700200006 (CURVE) Digitized data of Fig.4 2254700200007 COMMENT Of Authors. Measured data systematically lower than 2254700200008 comprehensive evaluations. Recommend to re-evaluate. 2254700200009 ENDBIB 7 0 2254700200010 NOCOMMON 0 0 2254700200011 DATA 3 8 2254700200012 EN DATA DATA-ERR 2254700200013 MEV B B 2254700200014 13.3 0.32 0.02 2254700200015 13.6 0.36 0.01 2254700200016 13.8 0.38 0.01 2254700200017 14.0 0.42 0.01 2254700200018 14.2 0.45 0.02 2254700200019 14.5 0.47 0.01 2254700200020 14.7 0.49 0.02 2254700200021 14.9 0.51 0.01 2254700200022 ENDDATA 10 0 2254700200023 ENDSUBENT 22 0 2254700299999 SUBENT 22547003 20080121 21932254700300001 BIB 4 7 2254700300002 REACTION (29-CU-63(N,2N)29-CU-62,,SIG) 2254700300003 Cross section measured by 2nd METHOD. 2254700300004 DECAY-DATA (29-CU-62,9.74MIN,DG,511.) 2254700300005 STATUS (PRELM) 2254700300006 (CURVE) Digitized data of Fig.4 2254700300007 COMMENT Of Authors. Measured data systematically lower than 2254700300008 comprehensive evaluations. Recommend to re-evaluate. 2254700300009 ENDBIB 7 0 2254700300010 NOCOMMON 0 0 2254700300011 DATA 3 6 2254700300012 EN DATA DATA-ERR 2254700300013 MEV B B 2254700300014 13.4 0.29 0.01 2254700300015 13.7 0.35 0.02 2254700300016 14.0 0.37 0.02 2254700300017 14.4 0.43 0.01 2254700300018 14.7 0.46 0.02 2254700300019 15.0 0.49 0.01 2254700300020 ENDDATA 8 0 2254700300021 ENDSUBENT 20 0 2254700399999 SUBENT 22547004 20080121 21932254700400001 BIB 4 7 2254700400002 REACTION (29-CU-65(N,2N)29-CU-64,,SIG) 2254700400003 DECAY-DATA (29-CU-64,12.699HR,DG,511.,.386) 2254700400004 STATUS (CURVE) Digitized data of Fig.5 2254700400005 (COREL,22089050) 2254700400006 COMMENT Of Authors. Measured data in good agreement within 2254700400007 exp. errors with data previously measured at FNS, 2254700400008 Entry 22089. 2254700400009 ENDBIB 7 0 2254700400010 NOCOMMON 0 0 2254700400011 DATA 3 8 2254700400012 EN DATA DATA-ERR 2254700400013 MEV B B 2254700400014 13.4 0.76 0.01 2254700400015 13.6 0.80 0.02 2254700400016 13.8 0.82 0.01 2254700400017 14.0 0.84 0.01 2254700400018 14.2 0.87 0.01 2254700400019 14.4 0.92 0.01 2254700400020 14.7 0.92 0.01 2254700400021 15.0 0.96 0.02 2254700400022 ENDDATA 10 0 2254700400023 ENDSUBENT 22 0 2254700499999 ENDENTRY 4 0 2254799999999