ENTRY 33045 20130524 31603304500000001 SUBENT 33045001 20130524 31603304500100001 BIB 10 34 3304500100002 TITLE Measurement of 56Fe(n,p)56Mn reaction cross-section 3304500100003 at En = 5.9,9.85,14.8 and 15.5 MeV. 3304500100004 AUTHOR (V.K.Mulik, H.Naik, S.V.Suryanarayana, S.D.Dhole, 3304500100005 P.M.Prajapati, B.S.Shivashankar, K.C.Jagadeesan, 3304500100006 S.V.Thakre, V.N.Bhoraskar, A.Goswami) 3304500100007 INSTITUTE (3INDPOO,3INDTRM,3INDBDA) 3304500100008 (3INDIND) Manipal University,Manipal 3304500100009 REFERENCE (J,JRN,296,1321,2013) 3304500100010 #doi:10.1007/s10967-013-2419-9 3304500100011 DETECTOR (HPGE) An 80 cm**3 HPGe detector coupled to a PC- 3304500100012 based 4K channel analyser. The energy resolution was 3304500100013 1.8 keV at 1.33 MeV gamma-ray energy of 60Co. The 3304500100014 photo-peak efficiency of the HPGe detector was 3304500100015 determined using standard gamma-ray sources such as 3304500100016 152Eu and 133Ba. 3304500100017 ANALYSIS The gamma peak areas were obtained by using PHAST 3304500100018 and GENIE-2K peak fitting programs. 3304500100019 ERR-ANALYS (ERR-T) Total uncertainties in the cross-section 3304500100020 includes statistical and systematic error described 3304500100021 below: 3304500100022 (ERR-S) Counting statistics (~4%) 3304500100023 (ERR-1) Uncertainty in decay data (~2%) 3304500100024 (ERR-2) Uncertainty in efficiency and energy 3304500100025 calibration of the detector (~3%) 3304500100026 (ERR-3) Uncertainty in monitor cross-section (~2%) 3304500100027 (ERR-4) Uncertainty in self-absorption of 3304500100028 gamma-rays(~2%) 3304500100029 (ERR-5) Uncertainty in neutron flux estimation (~4%) 3304500100030 ADD-RES Theoretical calculations using TALYS-1.4 and 3304500100031 EMPIRE-2.19 have been performed. 3304500100032 STATUS (TABLE) Table 2 of J. Rad. Nucl. Chem. 296(2013)1312 3304500100033 (APRVD) V.K. Mulik (2013-05-30) 3304500100034 HISTORY (20130524C) Compiled by V.K.Mulik,University of Pune, 3304500100035 vikas.mulik4@gmail.com 3304500100036 ENDBIB 34 0 3304500100037 COMMON 6 3 3304500100038 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 3304500100039 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3304500100040 4. 2. 3. 2. 2. 4. 3304500100041 ENDCOMMON 3 0 3304500100042 ENDSUBENT 41 0 3304500199999 SUBENT 33045002 20130524 31603304500200001 BIB 9 40 3304500200002 REACTION 1(26-FE-56(N,P)25-MN-56,,SIG) 3304500200003 2(26-FE-56(N,P)25-MN-56,,SIG) 3304500200004 MONITOR 1(49-IN-115(N,INL)49-IN-115-M,,SIG) 3304500200005 2(92-U-238(N,F),,SIG) 3304500200006 (92-U-238(N,F)40-ZR-97,CUM,FY) 3304500200007 DECAY-MON 1(49-IN-115-M,4.48HR,DG,336.2,0.459) 3304500200008 2(40-ZR-97,16.95HR,DG,743.0,0.928) 3304500200009 MONIT-REF 1(,,3,IRDF-2002,,2005) 5.9 MeV 3304500200010 2(20943003,B.Leugers+,C,76ANL,,246,1976) 9.85 MeV c.s 3304500200011 (21209002,B.Adams+,J,JNE/AB,14,85,1961) 15.5 MeV c.s. 3304500200012 (10828003,S.Naggy+,J,PR/C,17,163,1978) fission yield 3304500200013 (,T.C.Chapman+,J,PR/C,17,1089,1978) fission yield 3304500200014 DECAY-DATA (25-MN-56,2.57HR,DG,846.7,0.989) 3304500200015 FACILITY (VDGT,3INDTRM) 14 UD BARC-TIFR Pelletron facility at 3304500200016 Mumbai,India. 3304500200017 INC-SOURCE (P-LI7) The neutron beam was produced from the 7Li(p,n)3304500200018 reaction by using the proton beam. The thickness of 3304500200019 lithium and tantalum foils were 3.7 mg/cm**2 and 3304500200020 3.9 mg/cm**2 respectively. The In-Fe-U stack was 3304500200021 mounted at zero degree angle with respect to the proton3304500200022 beam direction at a distance ~ 1.8-2 cm from the 3304500200023 location of the Ta-Li-Ta stack. The incident proton 3304500200024 beam of energies were 7.8,12 and 18 MeV respectively. 3304500200025 The neutron flux were 3.03*10**6 n/cm2/s, 3304500200026 1.3*10**7 n/cm2/s and 1.53*10**7 n/cm2/s corresponding 3304500200027 to the average neutron energies of 5.9+-0.6, 9.85+-0.383304500200028 and 15.5+-0.7 MeV. 3304500200029 SAMPLE (26-FE-56,NAT=0.91754) The Iron sample (with purity 3304500200030 ~99.99%) in the form of thin metallic foil was used. A 3304500200031 known amount (60-170 mg) of the iron metal foil was 3304500200032 wrapped with 0.025 mm thick aluminum foil. Similarly, a3304500200033 known amount of indium (141-156 mg) and uranium 3304500200034 (570-990 mg) foil of the same size also wrapped 3304500200035 separately with 0.025 mm thick aluminum foil. The iron 3304500200036 foil was sandwiched between the In and U metal foil 3304500200037 and additionally wrapped with aluminum foil. 3304500200038 METHOD (ACTIV,GSPEC) The samples were irradiated for 15,4 and 3304500200039 5 hrs corresponding to the average neutron energies of 3304500200040 5.9+-0.6, 9.85+-0.38 and 15.5+-0.7 MeV. The samples 3304500200041 were cooled for 3-5 hrs after the irradiation. 3304500200042 ENDBIB 40 0 3304500200043 NOCOMMON 0 0 3304500200044 DATA 10 3 3304500200045 EN EN-ERR DATA 1ERR-T 1MONIT 1MONIT-ERR 13304500200046 DATA 2ERR-T 2MONIT 2MONIT-ERR 2 3304500200047 MEV MEV MB MB MB MB 3304500200048 MB MB MB MB 3304500200049 5.9 0.6 13.45 0.92 333. 13. 3304500200050 3304500200051 9.85 0.38 3304500200052 65.88 4.54 995. 23.9 3304500200053 15.5 0.7 3304500200054 76.22 5.25 1250. 30. 3304500200055 ENDDATA 10 0 3304500200056 ENDSUBENT 55 0 3304500299999 SUBENT 33045003 20130524 31603304500300001 BIB 9 17 3304500300002 REACTION (26-FE-56(N,P)25-MN-56,,SIG) 3304500300003 DECAY-DATA (25-MN-56,2.57HR,DG,846.7,0.989) 3304500300004 FACILITY (CCW,3INDPOO) An 8 curie tritium target was bombarded 3304500300005 by deuterium ions of energy ~ 175 keV at a deuteron 3304500300006 beam current ~ 80 uA. 3304500300007 INC-SOURCE (D-T) The 14 MeV neutrons were produced through 3304500300008 3H(d,n)4He reaction(Q=17.6 MeV). The neutron flux was 3304500300009 1.6x10**7 n/cm2/s. 3304500300010 SAMPLE (26-FE-56,NAT=0.91754) A known amount of Iron metal 3304500300011 foil(1.69 g) wrapped with the super pure aluminum 3304500300012 foil(744 mg) sealed in a polyethylene bag was used. 3304500300013 METHOD (ACTIV,GSPEC) The samples were irradiated for 30 3304500300014 mins. The samples were cooled for 4 mins after the 3304500300015 irradiation. 3304500300016 MONITOR (13-AL-27(N,P)12-MG-27,,SIG) 3304500300017 DECAY-MON (12-MG-27,9.45MIN,DG,843.7,0.718) 3304500300018 MONIT-REF (41240005,A.A.Filatenkov+,R,RI-252,1999) 3304500300019 ENDBIB 17 0 3304500300020 NOCOMMON 0 0 3304500300021 DATA 6 1 3304500300022 EN EN-ERR DATA ERR-T MONIT MONIT-ERR 3304500300023 MEV MEV MB MB MB MB 3304500300024 14.8 0.1 120.07 8.28 62.9 1.4 3304500300025 ENDDATA 3 0 3304500300026 ENDSUBENT 25 0 3304500399999 ENDENTRY 3 0 3304599999999