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