ENTRY 33043 20141212 31673304300000001 SUBENT 33043001 20141212 31673304300100001 BIB 18 54 3304300100002 TITLE Measurement of the neutron capture cross-section of 3304300100003 238-U using the neutron activation technique. 3304300100004 AUTHOR (H.Naik, S.V.Suryanarayana, V.K.Mulik, P.M.Prajapati, 3304300100005 B.S.Shivashankar, K.C.Jagadeesan, S.V.Thakare, D.Raj, 3304300100006 S.C.Sharma, P.V.Bhagwat, S.D.Dhole, S.Ganesan, 3304300100007 V.N.Bhoraskar, A.Goswami) 3304300100008 INSTITUTE (3INDTRM,3INDPOO,3INDBDA,3INDMNP) 3304300100009 REFERENCE (J,JRN,293,469,2012) 3304300100010 FACILITY (VDGT,3INDTRM) BARC-TIFR Pelletron facility at 3304300100011 TIFR,Mumbai. 3304300100012 INC-SOURCE (P-LI7)The neutron beam was obtained from the 7- 3304300100013 Li(p,n) reaction by using the proton beam. The 3304300100014 lithium foil was made up of natural lithium with 3304300100015 thickness of 3.7 mg/cm2, sandwiched between two 3304300100016 tantalum foils of different thickness. 3304300100017 SAMPLE The samples consist of natural 238-U metal foil and 3304300100018 natural indium metal foil, which were wrapped 3304300100019 separately with 0.025 mm thick aluminum foil to 3304300100020 prevent contamination from one to the other. 3304300100021 The size of 238-U metal foil was 1.0 cm2 with 3304300100022 thickness of 29.3 mg/cm2, whereas indium metal foil 3304300100023 is also of same size with thickness of 2.6 mg/cm2. 3304300100024 DETECTOR (HPGE) The gamma-rays of reaction products from the 3304300100025 irradiated U and In samples were counted in an energy 3304300100026 and efficiency calibrated 80 c.c. HPGe detector 3304300100027 coupled to a PC-based 4K channel analyzer. 3304300100028 METHOD (ACTIV,GSPEC) Irradiated for 4-6 hrs, cooled for 1 hr. 3304300100029 PART-DET (G) 3304300100030 MONITOR (49-IN-115(N,INL)49-IN-115-M,,SIG) 3304300100031 DECAY-MON (49-IN-115-M,4.486HR,DG,336.2,0.459) 3304300100032 MONIT-REF (,,3,IRDF-2002,,2005) 3304300100033 CORRECTION Contribution of tail neutrons was estimated by folding 3304300100034 of evaluated (n,g) and (n,2n) cross sections in 3304300100035 ENDF/B-VII.1 and JENDL-4.0 libraries by neutron 3304300100036 spectra given in C.H.Poppe et al. (1976) and 3304300100037 J.W.Meadows et al. (1972), and subtracted. 3304300100038 REL-REF (R,,C.H.Poppe+,J,PR/C,14,438,1976) 3304300100039 7Li(p,n) neutron spectrum given 3304300100040 (R,,J.W.Meadows+,R,ANL-7983,1972) 3304300100041 7Li(p,n) neutron spectrum given 3304300100042 ERR-ANALYS (ERR-T) The overall uncertainty is the quadratic sum of3304300100043 both statistical and systematic errors 3304300100044 (ERR-S,10.,15.)Counting statistics (~10-15%) 3304300100045 (ERR-SYS) Total systematic uncertainty includes: 3304300100046 (ERR-1)Neutron flux estimation (~4%) 3304300100047 (ERR-2)Irradiation time (~2%) 3304300100048 (ERR-3)Detection efficiency calibration (~3%) 3304300100049 (ERR-4)Half-life of the fission products and the 3304300100050 gamma-ray abundances (~2%) 3304300100051 STATUS (TABLE) Table 2 of J. Rad. Nucl. Chem. 293(2012)469 3304300100052 (APRVD) Entry approved by Dr. H.Naik 3304300100053 HISTORY (20130220C)Compiled by V.K.Mulik,University of Pune, 3304300100054 vikas.mulik4@gmail.com 3304300100055 (20141212U) BIB minor corrections in 003 3304300100056 ENDBIB 54 0 3304300100057 COMMON 5 3 3304300100058 ERR-SYS ERR-1 ERR-2 ERR-3 ERR-4 3304300100059 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3304300100060 6. 4. 2. 3. 2. 3304300100061 ENDCOMMON 3 0 3304300100062 ENDSUBENT 61 0 3304300199999 SUBENT 33043002 20130220 31593304300200001 BIB 5 10 3304300200002 REACTION (92-U-238(N,G)92-U-239,,SIG) 3304300200003 DECAY-DATA (92-U-239,23.54MIN,DG,74.7,0.522) 3304300200004 (93-NP-239,2.355D,DG,103.7,0.239, 3304300200005 DG,106.1,0.227,DG,228.2,0.107,DG,277.9,0.142) 3304300200006 RAD-DET (93-NP-239,DG) 3304300200007 INC-SPECT At average neutron energy of 3.7 MeV, the neutron 3304300200008 flux was (8.78 +- 0.38) x 10**6 n/cm2/s. The neutron 3304300200009 flux for (n,gamma) reaction at average neutron energy 3304300200010 of 9.85 +- 0.38 MeV was (1.3 +- 0.05) x 10**7 n/cm2/s 3304300200011 MISC-COL (MISC) Cross sections not corrected for tail neutrons 3304300200012 ENDBIB 10 0 3304300200013 NOCOMMON 0 0 3304300200014 DATA 6 2 3304300200015 EN EN-ERR DATA ERR-T MISC MISC-ERR 3304300200016 MEV MEV MB MB MB MB 3304300200017 3.7 0.3 11.6 1.0 15.711 0.986 3304300200018 9.85 0.38 1.42 0.09 2.242 0.091 3304300200019 ENDDATA 4 0 3304300200020 ENDSUBENT 19 0 3304300299999 SUBENT 33043003 20141212 31673304300300001 BIB 5 8 3304300300002 REACTION (92-U-238(N,2N)92-U-237,,SIG) 3304300300003 DECAY-DATA (92-U-237,6.75D,DG,101.1,0.260,DG,208.0,0.220) 3304300300004 INC-SPECT The neutron flux for (n,2n) reaction at average 3304300300005 neutron energy of 9.85 +- 0.38 MeV corresponding 3304300300006 to proton energy of 12 MeV was obtained to be 3304300300007 (6.5 +- 0.25) x 10**6 n/cm2/s. 3304300300008 MISC-COL (MISC) Cross sections not corrected for tail neutrons 3304300300009 HISTORY (20141212U) BIB minor corrections 3304300300010 ENDBIB 8 0 3304300300011 NOCOMMON 0 0 3304300300012 DATA 6 1 3304300300013 EN EN-ERR DATA ERR-T MISC MISC-ERR 3304300300014 MEV MEV MB MB MB MB 3304300300015 9.85 0.38 1311. 87. 1351. 87. 3304300300016 ENDDATA 3 0 3304300300017 ENDSUBENT 16 0 3304300399999 ENDENTRY 3 0 3304399999999