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