ENTRY G0014 20120906 G026G001400000001 SUBENT G0014001 20120906 G026G001400100001 BIB 14 60 G001400100002 TITLE Post-neutron mass yield distribution and photo-neutron G001400100003 cross-section measurements in 209-Bi with 65-MeV G001400100004 bremsstrahlung G001400100005 AUTHOR (H.Naik, A.V.Reddy, S.Ganesan, D.Raj, Kwangsoo Kim, G001400100006 Guinyun Kim, Young Do Oh, Due Khue Pham, Moo-Hyun Cho,G001400100007 In Soo Ko, Won Namkung) G001400100008 INSTITUTE (3INDTRM,3KORPUE) G001400100009 REFERENCE (J,KPS,52,934,2008) G001400100010 REL-REF (O,G0019009,H.Naik+,J,EPJ/A,41,323,2009) G001400100011 Final average mass value (103.1+/-20.5 amu) given G001400100012 FACILITY (LINAC,3KORPUE) G001400100013 INC-SOURCE (BRST) The target assembly was irradiated for 5-7 G001400100014 hours with bremsstrahlung produced by bombarding the G001400100015 65-MeV electrons on the 0.1 mm thick tungsten foil. G001400100016 SAMPLE A metal of 209Bi target (74.417 g) of 25 cm*2 area G001400100017 was wrapped with 0.0025 cm thick super pure-aluminum G001400100018 foil and was fixed on a stand at proper height behind G001400100019 a 0.1 mm thick tungsten metal foil situated in a G001400100020 fixed position. G001400100021 The tungsten metal foil acts as a an electron- G001400100022 bremsstrahlung converter whereas aluminum foil act as G001400100023 a recoil catcher of fission product from the bismuth G001400100024 metal foil during irradiation. G001400100025 DETECTOR (HPGE) The gamma-ray activities of the samples with G001400100026 fixed geometry were measured one after another by G001400100027 using an energy and efficiency calibrated HPGe G001400100028 detector coupled to a PC based 4K-channel analyzer. G001400100029 METHOD (GSPEC) The post-neutron emission mass yield G001400100030 distribution and the photo-neutron cross-section of G001400100031 209Bi with 65-MeV bremsstrahlung have been determined G001400100032 using an off-line gamma-ray spectrometric technique. G001400100033 ANALYSIS The photo-peak areas of different gamma-rays of the G001400100034 nuclides of interest were calculated by subtracting G001400100035 the linear Compton background from their total net G001400100036 peak areas. G001400100037 From the gamma-ray activities of the fission products, G001400100038 their yields were calculated using decay equation. G001400100039 Similarly from the gamma-ray activities of the G001400100040 reaction product, photo-neutron (g,3n) cross-section G001400100041 was also calculated using similar decay equation. G001400100042 ERR-ANALYS (ERR-T) The uncertainties shown in the measured G001400100043 cumulative yields of individual fission products and G001400100044 photo-neutron cross sections of 209-Bi are the G001400100045 precision values from two determinations. G001400100046 The overall uncertainty represents contributions from G001400100047 both random and systematic errors. G001400100048 The random error in the observed activity is due to G001400100049 counting statistics and is estimated to be 10-15%. G001400100050 The overall systematic error is about 4%. G001400100051 The total error is around 11-16%. G001400100052 The systematic errors are due to uncertainties in G001400100053 (ERR-1) irradiation time (2%) G001400100054 (ERR-2) detection efficiency calibration (3%) G001400100055 (ERR-3) half-life of fission and the reaction product (G001400100056 (ERR-4) gamma-ray abundance (1%) G001400100057 STATUS (APRVD) Entry approved by Dr. H. Naik G001400100058 HISTORY (20080421C) Paresh Prajapati, Sarbjit Singh G001400100059 (20080525A) VV CDFE. Last REACTION codes corrected G001400100060 (20090121A) On. 002: REACTION and data table updated G001400100061 (20120906U) On. REL-REF added, ANALYSIS=AREA deleted. G001400100062 ENDBIB 60 0 G001400100063 COMMON 4 3 G001400100064 ERR-1 ERR-2 ERR-3 ERR-4 G001400100065 PER-CENT PER-CENT PER-CENT PER-CENT G001400100066 2. 3. 1. 1. G001400100067 ENDCOMMON 3 0 G001400100068 ENDSUBENT 67 0 G001400199999 SUBENT G0014002 20090121 G020G001400200001 BIB 6 10 G001400200002 REACTION 1((83-BI-209(G,F)ELEM/MASS,CUM,FY,,BRA)/ G001400200003 (83-BI-209(G,F)44-RU-103,CUM,FY,,BRA)) G001400200004 2(83-BI-209(G,F)ELEM/MASS,CUM,FY,,BRA) G001400200005 MONITOR 2((MONIT)83-BI-209(G,F)44-RU-103,CUM,FY,,BRA) G001400200006 COMMENT H.Naik (2010-01-16, through G.N.Kim) G001400200007 105Ru -> 105Rh in the Table 1 of the KPS article G001400200008 REL-REF (N,G0019001,H.Naik+,J,EPJ/A,14,323,2009) G001400200009 Absolute fission yield is given G001400200010 STATUS (TABLE) Table 1 of J,KPS,52,934,2008 G001400200011 HISTORY (20090121A) On. REACTION and data table updated G001400200012 ENDBIB 10 0 G001400200013 COMMON 2 3 G001400200014 EN-MAX MONIT 2 G001400200015 MEV PC/FIS G001400200016 65.0 8.496 G001400200017 ENDCOMMON 3 0 G001400200018 DATA 6 14 G001400200019 ELEMENT MASS DATA 1ERR-T 1DATA 2ERR-T 2G001400200020 NO-DIM NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS G001400200021 38. 91. 0.443 0.082 3.764 0.697 G001400200022 40. 89. 0.314 0.058 2.668 0.493 G001400200023 40. 95. 0.723 0.069 6.143 0.586 G001400200024 40. 95. 0.693 0.087 5.888 0.739 G001400200025 40. 97. 0.857 0.091 7.281 0.773 G001400200026 42. 99. 0.934 0.129 7.935 1.096 G001400200027 44. 103. 8.496 0.850 G001400200028 45. 105. 0.959 0.013 8.148 0.110 G001400200029 47. 112. 0.675 0.056 5.735 0.476 G001400200030 47. 112. 0.627 0.172 5.327 1.461 G001400200031 47. 113. 0.579 0.189 4.919 0.606 G001400200032 48. 115. 0.471 0.021 4.002 0.178 G001400200033 48. 117. 0.090 0.017 0.765 0.144 G001400200034 48. 117. 0.144 0.015 1.223 0.127 G001400200035 ENDDATA 16 0 G001400200036 ENDSUBENT 35 0 G001400299999 SUBENT G0014003 20080421 G017G001400300001 BIB 3 13 G001400300002 REACTION (83-BI-209(G,3N)83-BI-206,,SIG,,BRA) G001400300003 DECAY-DATA ((1.)83-BI-206,6.243D,DG,343.51,0.2343) G001400300004 ((2.)83-BI-206,6.243D,DG,398.00,0.1074) G001400300005 ((3.)83-BI-206,6.243D,DG,516.18,0.4070) G001400300006 ((4.)83-BI-206,6.243D,DG,537.45,0.3050) G001400300007 ((5.)83-BI-206,6.243D,DG,632.25,0.0476) G001400300008 ((6.)83-BI-206,6.243D,DG,803.10,0.9900) G001400300009 ((7.)83-BI-206,6.243D,DG,881.01,0.6620) G001400300010 ((8.)83-BI-206,6.243D,DG,895.12,0.1566) G001400300011 ((9.)83-BI-206,6.243D,DG,1018.63,0.135) G001400300012 ((10.)83-BI-206,6.243D,DG,1718.70,0.3804) G001400300013 STATUS (TABLE) Data are taken from table 2. Measured photo G001400300014 neutron cross-section determined in the present work. G001400300015 ENDBIB 13 0 G001400300016 COMMON 1 3 G001400300017 EN-MAX G001400300018 MEV G001400300019 65.0 G001400300020 ENDCOMMON 3 0 G001400300021 DATA 3 10 G001400300022 DATA ERR-T DECAY-FLAG G001400300023 MB MB NO-DIM G001400300024 1.060 0.162 1. G001400300025 1.065 0.165 2. G001400300026 1.215 0.251 3. G001400300027 1.208 0.191 4. G001400300028 1.309 0.195 5. G001400300029 1.501 0.173 6. G001400300030 1.543 0.188 7. G001400300031 1.499 0.201 8. G001400300032 1.495 0.214 9. G001400300033 1.452 0.222 10. G001400300034 ENDDATA 12 0 G001400300035 ENDSUBENT 34 0 G001400399999 SUBENT G0014004 20080421 G017G001400400001 BIB 2 14 G001400400002 REACTION (83-BI-209(G,3N)83-BI-206,,SIG) G001400400003 COMMENT It can be seen from Table 2 that the photo-neutron G001400400004 (G,3N) cross-section of 209-Bi at a 65-MeV G001400400005 bremsstrahlung energy increases with increasing gamma G001400400006 ray energy of the 206-Bi up to 803 KeV and then remainsG001400400007 constant above that energy. This is because of the use G001400400008 of thick bismuth metal foil of 2 mm, which causes G001400400009 attenuation of the gamma rays of 206-Bi to different G001400400010 extents depending upon the energy. Above 803 keV, the G001400400011 attenuation of gamma -rays in a 2-mm thick bismuth foilG001400400012 is negligible. Photo-neutron (G,3N) cross-section of G001400400013 1.478(0.054) mb was obtained after averaging the G001400400014 experimentally determined value for the gamma energies G001400400015 of 803 keV and above. G001400400016 ENDBIB 14 0 G001400400017 NOCOMMON 0 0 G001400400018 DATA 3 1 G001400400019 EN-MAX DATA ERR-T G001400400020 MEV MB MB G001400400021 65.0 1.478 0.054 G001400400022 ENDDATA 3 0 G001400400023 ENDSUBENT 22 0 G001400499999 ENDENTRY 4 0 G001499999999