ENTRY 33059 20150124 31713305900000001 SUBENT 33059001 20150124 31713305900100001 BIB 14 44 3305900100002 TITLE Measurement of the 238U(n,c)239U and 238U(n,2n)237U 3305900100003 Reaction Cross Sections Using a Neutron Activation 3305900100004 Technique at Neutron Energies of 8.04 and 11.90 MeV 3305900100005 AUTHOR (R.Crasta,S.Ganesh,H.Naik,A.Goswami,S.V.Suryanarayana, 3305900100006 S.C.Sharma,P.V.Bhagwat,B.S.Shivashankar,V.K.Mulik, 3305900100007 P.M.Prajapati) 3305900100008 INSTITUTE (3INDMNG,3INDTRM,3INDPOO,3INDBDA,3INDMNP) 3305900100009 FACILITY (VDGT,3INDTRM) 14 UD BARC TIFR Pelletron Facility 3305900100010 REFERENCE (J,NSE,178,66,2014) 3305900100011 #doi:10.13182/NSE11-90 3305900100012 SAMPLE Separate sets of samples were made for irradiation 3305900100013 for two different neutron energies. In the first set 3305900100014 the thickness of uranium foil is 395.1 mg/cm2, 3305900100015 whereas in the second set it is 344.1 mg/cm2. 3305900100016 INC-SOURCE (P-LI7) Natural Lithium with 3.7 mg/cm2 thickness is 3305900100017 sandwiched between two tantalum foils of different 3305900100018 thicknesses. 3305900100019 DETECTOR (HPGE) The detector efficiency was 20% at 1332.5 keV. 3305900100020 The resolution of the detector system had a 3305900100021 full-width at half maximum of 1.8 keV at 1332.5 keV 3305900100022 of 60Co. 3305900100023 METHOD (ACTIV) The samples were irradiated for 5 to 7 h 3305900100024 depending upon the proton beam energy facing the 3305900100025 tantalum target. The proton beam energies were 10 and 3305900100026 14 MeV. The corresponding average neutron energies 3305900100027 impinging on the U targets were 8.04 +- 0.30 MeV and 3305900100028 11.90 +- 0.35 MeV, respectively. The irradiated 3305900100029 samples were cooled for 3 to 4 h. 3305900100030 ERR-ANALYS (ERR-T) Total uncertainty propagated from: 3305900100031 (ERR-S,5.,10.) Statistical error 3305900100032 (ERR-SYS) Systematic error (6%) 3305900100033 (ERR-1) Neutron flux estimation (~ 4%) 3305900100034 (ERR-2) Irradiation time (~2%) 3305900100035 (ERR-3) Detector efficiency (~3%) 3305900100036 (ERR-4) Half life of fission product (~2%) 3305900100037 MONITOR (92-U-238(N,F)53-I-135,,SIG) 3305900100038 (92-U-238(N,F)40-ZR-97,,SIG) 3305900100039 MONIT-REF (,S.Nagy+,J,PR/C,17,163,1978) 3305900100040 (,M.Rajagopalan+,J,JIN,38,351,1976) 3305900100041 CORRECTION Corrected for captures by low energy backgroud (tail) 3305900100042 neutrons 3305900100043 HISTORY (20150124C) M Balasubramaniam, S.Subramanian, 3305900100044 C.Karthikraj Bharathiar University Coimbatore, 3305900100045 V.O.Chidamabaram College, Thoothukudi, Tamilnadu 3305900100046 ENDBIB 44 0 3305900100047 COMMON 5 3 3305900100048 ERR-SYS ERR-1 ERR-2 ERR-3 ERR-4 3305900100049 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3305900100050 6. 4. 2. 3. 2. 3305900100051 ENDCOMMON 3 0 3305900100052 ENDSUBENT 51 0 3305900199999 SUBENT 33059002 20150124 31713305900200001 BIB 4 8 3305900200002 REACTION (92-U-238(N,G)92-U-239,,SIG) 3305900200003 DECAY-DATA (93-NP-239,2.357D,DG,103.7,0.239, 3305900200004 DG,106.1,0.227, 3305900200005 DG,228.2,0.108, 3305900200006 DG,277.6,0.144) 3305900200007 COMMENT Haladhara Naik (2015-09-08): The 74.7 keV activity was 3305900200008 not used for 239U(n,g)239U cross-section calculation. 3305900200009 STATUS (TABLE) Table 2 of Nucl. Sci. Eng. 178(2014)66 3305900200010 ENDBIB 8 0 3305900200011 NOCOMMON 0 0 3305900200012 DATA 4 2 3305900200013 EN EN-ERR DATA ERR-T 3305900200014 MEV MEV MB MB 3305900200015 8.04 0.3 1.07 0.24 3305900200016 11.9 0.35 1.12 0.33 3305900200017 ENDDATA 4 0 3305900200018 ENDSUBENT 17 0 3305900299999 SUBENT 33059003 20150124 31713305900300001 BIB 3 4 3305900300002 REACTION (92-U-238(N,2N)92-U-237,,SIG) 3305900300003 DECAY-DATA (92-U-237,6.75D,DG,101.1,0.26, 3305900300004 DG,208.0,0.212) 3305900300005 STATUS (TABLE) Table 2 of Nucl. Sci. Eng. 178(2014)66 3305900300006 ENDBIB 4 0 3305900300007 NOCOMMON 0 0 3305900300008 DATA 4 2 3305900300009 EN EN-ERR DATA ERR-T 3305900300010 MEV MEV MB MB 3305900300011 8.04 0.3 1044.05 123.95 3305900300012 11.9 0.35 1231.39 153.41 3305900300013 ENDDATA 4 0 3305900300014 ENDSUBENT 13 0 3305900399999 ENDENTRY 3 0 3305999999999