ENTRY 22825 20130208 22342282500000001 SUBENT 22825001 20130208 22342282500100001 BIB 19 66 2282500100002 TITLE .Measurements of isomeric cross sections for (n,2n) 2282500100003 reaction on 140Ce, 142Nd and 144Sm isotopes 2282500100004 around 14 MeV incident neutron energy 2282500100005 AUTHOR (I.A.Reyhancan,M.Bostan,A.Durusoy,A.Elmali, A.Baykal, 2282500100006 Y.Oezbir) 2282500100007 INSTITUTE (2TUKCNA) Reyhancan, Elmali, Baykal, Oezbir 2282500100008 (2TUKSTU) Bostan 2282500100009 (2TUKYTU) Durusoy 2282500100010 REFERENCE (J,ANE,30,1539,2003) Main reference, data given 2282500100011 REL-REF (I,22478001,M.Subasi+,J,NSE,130,254,1998) Experimental2282500100012 details 2282500100013 (I,22392001,E.Gueltekin+,J,ANE,28,53,2001) Details of 2282500100014 the experimental arrangement 2282500100015 (I,22474001,M.Subasi+,J,NSE,122,423,1996) Details of 2282500100016 the germanium high-purity detector 2282500100017 (M,,B.Anders,R,GKSS-83-E25,1983) Description of the 2282500100018 cyclic activation method 2282500100019 FACILITY (VDG,2TUKCNA) Neutron generator 'SAMES T-400'. 2282500100020 Terminal voltage is 250 KV, average beam current 300 2282500100021 micro-amperes 2282500100022 INC-SOURCE (D-T) 2282500100023 INC-SPECT .Angles of irradiation of the target by deuterium ion 2282500100024 beam are 0, 30, 60, 90, 120 and 130 degrees. Effective2282500100025 mean neutron energy at each sample position had been 2282500100026 previously determined by the ratio of 90Zr(n,2n)89Zr 2282500100027 and 93Nb(n,2n)92m-Nb cross sections 2282500100028 .Neutron fluxes ranged from 1.E+7 to 6.E+7 n/cm2/sec 2282500100029 ANALYSIS .Cross sections were derived from the cyclic activation2282500100030 formulas by Anders, see REL-REF #4 2282500100031 METHOD (ACTIV) Activation 2282500100032 (SITA) Single target irradiation 2282500100033 PART-DET (G,N) 2282500100034 DETECTOR (HPGE) Coaxial detector 'CANBERRA', volume 82 cm3 with 2282500100035 1.79 keV full width at half-maximum of 1333 keV 2282500100036 gamma-energy. An acrylic plate of 10 mm thickness 2282500100037 was placed in front of the detector to block 2282500100038 the beta particles from the sample 2282500100039 (SCIN) Plastic scintillation detector NE102A for 2282500100040 neutron flux monitoring 2282500100041 MONITOR (13-AL-27(N,P)12-MG-27,,SIG) 2282500100042 DECAY-MON (12-MG-27,9.458MIN,DG,843.8,0.73) 2282500100043 MONIT-REF (41240000,A.Filatenkov+,R,INDC(CCP)-402,1997) 2282500100044 CORRECTION .Corrections were made for self-absorption of gammas 2282500100045 in samples, random coincidence, dead time and 2282500100046 fluctuation of neutron flux 2282500100047 ADD-RES (THEO) Statistical model calculation 2282500100048 ERR-ANALYS (ERR-T) Total error 2282500100049 (ERR-1) Error of the sample weight 2282500100050 (ERR-2) Error due to concentration of the elements 2282500100051 in samples 2282500100052 (ERR-3,0.2,2.3) Error due to isotopic abundance 2282500100053 min error is 0.2% 2282500100054 (ERR-4) Aprx error due to relative gamma-ray intensity2282500100055 (ERR-5) Error due to the efficiency of gamma 2282500100056 detector and due to counting solid angle 2282500100057 (ERR-6,0.6,1.3) Error due to full energy 2282500100058 photo-peak area 2282500100059 (ERR-7) Error due to neutron flux fluctuations 2282500100060 (ERR-8) Error of irradiation, cooling and measuring 2282500100061 times 2282500100062 (MONIT-ERR) Error due to effective neutron flux 2282500100063 = reference cross section 2282500100064 HISTORY (20010611C) + + J.O.S. 2282500100065 (20040131U) Last checking has been done. 2282500100066 (20130208U) SD: FACILITY was changed (LINAC -> VDG). 2282500100067 ERR-ANALYS corrected. 2282500100068 ENDBIB 66 0 2282500100069 COMMON 7 6 2282500100070 ERR-1 ERR-2 ERR-4 ERR-5 ERR-7 ERR-8 2282500100071 MONIT-ERR 2282500100072 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2282500100073 PER-CENT 2282500100074 0.1 0.1 0.4 3. 1. 0.12282500100075 3. 2282500100076 ENDCOMMON 6 0 2282500100077 ENDSUBENT 76 0 2282500199999 SUBENT 22825002 20040131 00002282500200001 BIB 4 8 2282500200002 REACTION (58-CE-140(N,2N)58-CE-139-M,,SIG) 2282500200003 DECAY-DATA (58-CE-139-M,56.54SEC,DG,754.24,0.9245) 2282500200004 SAMPLE .Cerium oxide powder Ce-O2, 99.9% purity, pressed to 2282500200005 pellets 13 mm diameter, 8.5 mm thick, in stainless 2282500200006 steel capsules, weight aprx 2 gram, natural isotopic 2282500200007 abundance, Ce-140 content is 88.45+-0.18% 2282500200008 ERR-ANALYS (ERR-HL ) Error of the half-life 2282500200009 (ERR-IDD ) Error of the decay gamma intensity 2282500200010 ENDBIB 8 0 2282500200011 COMMON 2 3 2282500200012 ERR-HL ERR-IDD 2282500200013 SEC PER-CENT 2282500200014 0.13 0.3 2282500200015 ENDCOMMON 3 0 2282500200016 DATA 5 6 2282500200017 EN EN-ERR DATA ERR-T MONIT 2282500200018 MEV MEV MB MB MB 2282500200019 13.57 0.04 875. 38. 76.64 2282500200020 13.75 0.05 833. 36. 73.88 2282500200021 14.15 0.07 798. 34. 70.32 2282500200022 14.52 0.09 866. 37. 67.31 2282500200023 14.75 0.09 953. 41. 64.10 2282500200024 14.83 0.10 930. 40. 62.56 2282500200025 ENDDATA 8 0 2282500200026 ENDSUBENT 25 0 2282500299999 SUBENT 22825003 20040131 00002282500300001 BIB 4 8 2282500300002 REACTION (60-ND-142(N,2N)60-ND-141-M,,SIG) 2282500300003 DECAY-DATA (60-ND-141-M,62.0SEC,DG,756.7,0.914) 2282500300004 SAMPLE .Nejdymium oxide powder Nd2-O3, 99.9% purity, pressed 2282500300005 to pellets 13 mm diameter, 8.5 mm thick, in stainless 2282500300006 steel capsules, weight aprx 2 gram, natural isotopic 2282500300007 abundance, Nd-142 content is 27.2+-0.5% 2282500300008 ERR-ANALYS (ERR-HL ) Error of the half-life 2282500300009 (ERR-IDD ) Error of the decay gamma intensity 2282500300010 ENDBIB 8 0 2282500300011 COMMON 2 3 2282500300012 ERR-HL ERR-IDD 2282500300013 SEC PER-CENT 2282500300014 0.8 0.4 2282500300015 ENDCOMMON 3 0 2282500300016 DATA 5 6 2282500300017 EN EN-ERR DATA ERR-T MONIT 2282500300018 MEV MEV MB MB MB 2282500300019 13.57 0.04 646. 30. 76.64 2282500300020 13.75 0.05 726. 34. 73.88 2282500300021 14.15 0.07 671. 32. 70.32 2282500300022 14.52 0.09 727. 34. 67.31 2282500300023 14.75 0.09 699. 33. 64.10 2282500300024 14.83 0.10 711. 33. 62.56 2282500300025 ENDDATA 8 0 2282500300026 ENDSUBENT 25 0 2282500399999 SUBENT 22825004 20040131 00002282500400001 BIB 4 7 2282500400002 REACTION (62-SM-144(N,2N)62-SM-143-M,,SIG) 2282500400003 DECAY-DATA (62-SM-143-M,66.SEC,DG,754.0,1.0) 2282500400004 SAMPLE .Samarium oxide powder Sm2-O3, 99.9% purity, pressed 2282500400005 to pellets 13 mm diameter, 8.5 mm thick, in stainles S2282500400006 steel capsules, weight aprx 2 gram, natural isotopic 2282500400007 abundance, Sm-144 content is 3.07+-0.07% 2282500400008 ERR-ANALYS (ERR-HL ) Error of the half-life 2282500400009 ENDBIB 7 0 2282500400010 COMMON 1 3 2282500400011 ERR-HL 2282500400012 SEC 2282500400013 2. 2282500400014 ENDCOMMON 3 0 2282500400015 DATA 5 6 2282500400016 EN EN-ERR DATA ERR-T MONIT 2282500400017 MEV MEV MB MB MB 2282500400018 13.57 0.04 397. 16. 76.64 2282500400019 13.75 0.05 424. 17. 73.88 2282500400020 14.15 0.07 432. 18. 70.32 2282500400021 14.52 0.09 486. 20. 67.31 2282500400022 14.75 0.09 597. 25. 64.10 2282500400023 14.83 0.10 635. 26. 62.56 2282500400024 ENDDATA 8 0 2282500400025 ENDSUBENT 24 0 2282500499999 ENDENTRY 4 0 2282599999999