ENTRY 10314 20171207 14391031400000001 SUBENT 10314001 20171207 14391031400100001 BIB 11 32 1031400100002 TITLE Absolute measurements of 235U and 239PU fission 1031400100003 cross-sections with photoneutron sources 1031400100004 AUTHOR (M.C.Davis, G.F.Knoll, J.C.Robertson, D.M.Gilliam) 1031400100005 INSTITUTE (1USAMHG) 1031400100006 REFERENCE (J,ANE,5,569,1978) 1031400100007 INC-SOURCE (PHOTO) Photoneutron sources: Na-Be (964 keV), 1031400100008 La-Be (770 keV), Na-D (265 keV), and Ga-D (140 keV). 1031400100009 METHOD (MANGB) 1031400100010 DETECTOR (TRD) Pair of limited solid angle track-etch detectors 1031400100011 MONITOR Efficiency of manganese bath determined relative 1031400100012 to secondary national standard source NBS-II. 1031400100013 CORRECTION Corrected for 1031400100014 - fragment emission anisotropy 1031400100015 - angular distribution normalization to lab. 1031400100016 - D(g,n) reaction in solution 1031400100017 - parasitic absorption 1031400100018 - leakage 1031400100019 - scattering in Pt backings 1031400100020 - scattering in foil holder (239Pu only) 1031400100021 - scattering in other structures 1031400100022 - foil impurities 1031400100023 - energy spectrum. 1031400100024 STATUS (APRVD) Approved by author 1031400100025 HISTORY (19741015C) AP 1031400100026 (19751216A) Data and reference updated 1031400100027 (19760608A) Data and reference updated 1031400100028 (19781208A) Reference and data updated. 1031400100029 (19790315A) Reference updated. BIB corrections. 1031400100030 (20020823A) Updated to new date formats, lower case. 1031400100031 (20170724A) On. ERR-ANALYS updated. CORRECTOIN added. 1031400100032 Major revsion in 002+003. 004 added. 1031400100033 (20171207A) On. Major revision in 002-003. 1031400100034 ENDBIB 32 0 1031400100035 NOCOMMON 0 0 1031400100036 ENDSUBENT 35 0 1031400199999 SUBENT 10314002 20171207 14391031400200001 BIB 5 24 1031400200002 REACTION (92-U-235(N,F),,SIG) 1031400200003 SAMPLE U3O8 deposits of 8.16 and 6.85 mg on Pt (+/-30 ug). 1031400200004 The mass was determined by microbalance weighings 1031400200005 and confirmed by thermal neutron fission and alpha 1031400200006 counting. 1031400200007 ERR-ANALYS (ERR-T) Total uncertainty 1031400200008 (ERR-1,,,U) Net fission counts/source neutron 1031400200009 (ERR-2,,,U) Manganese bath comparison of sources 1031400200010 (ERR-3,,,C) Fragment emission anisotropy 1031400200011 (ERR-4,,,C) Angular distribution normalization to lab.1031400200012 (ERR-5,,,C) Half-life extrapolation 1031400200013 (ERR-6,,,F) NBS-II reference source (0.50%) 1031400200014 (ERR-7,,,F) Fissile foil masses (0.50%) 1031400200015 (ERR-8,,,C) Scattering in Pt backings 1031400200016 (ERR-9,,,C) Scattering in other structures 1031400200017 (ERR-10,,,U) Compensated beam geometry (0.57%) 1031400200018 (ERR-11,,,C) Energy spectrum (0.30%) 1031400200019 (ERR-12,,,U) Aperture diameter (0.13%) 1031400200020 (ERR-13,,,U) Deposit-aperture distance (0.14%) 1031400200021 STATUS (TABLE) Tables 6 and 8 of Ann.Nucl.Energy 5(1978)569 1031400200022 HISTORY (19790315A) Data updated. 1031400200023 (20170724A) On. Partial uncertainties added. 1031400200024 DATA-ERR -> ERR-T and %-uncertainties adopted for it. 1031400200025 (20171207A) On. ERR-12 and ERR-13 added. 1031400200026 ENDBIB 24 0 1031400200027 COMMON 6 3 1031400200028 ERR-6 ERR-7 ERR-10 ERR-11 ERR-12 ERR-13 1031400200029 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1031400200030 0.50 0.50 0.57 0.30 0.13 0.14 1031400200031 ENDCOMMON 3 0 1031400200032 DATA 10 4 1031400200033 EN DATA ERR-T ERR-1 ERR-2 ERR-3 1031400200034 ERR-4 ERR-5 ERR-8 ERR-9 1031400200035 KEV B PER-CENT PER-CENT PER-CENT PER-CENT 1031400200036 PER-CENT PER-CENT PER-CENT PER-CENT 1031400200037 140. 1.471 2.16 1.39 0.25 1.17 1031400200038 0.12 0.57 0.21 0.17 1031400200039 265. 1.274 2.11 1.51 0.26 1.03 1031400200040 0.11 0.25 0.20 0.19 1031400200041 770. 1.162 2.01 1.00 0.25 1.37 1031400200042 0.06 0.25 0.32 0.18 1031400200043 964. 1.195 1.98 1.18 0.26 1.12 1031400200044 0.05 0.25 0.38 0.24 1031400200045 ENDDATA 12 0 1031400200046 ENDSUBENT 45 0 1031400299999 SUBENT 10314003 20171207 14391031400300001 BIB 5 24 1031400300002 REACTION (94-PU-239(N,F),,SIG) 1031400300003 SAMPLE PuO2 deposits of 5.59 and 4.94 mg on Pt (+/-1.4%). 1031400300004 The mass was determined by microbalance weighings 1031400300005 and confirmed by thermal neutron fission and alpha 1031400300006 counting. 1031400300007 ERR-ANALYS (ERR-T) Total uncertainty 1031400300008 (ERR-1,,,U) Net fission counts/source neutron 1031400300009 (ERR-2,,,U) Manganese bath comparison of sources 1031400300010 (ERR-3,,,C) Fragment emission anisotropy 1031400300011 (ERR-4,,,C) Angular distribution normalization to lab.1031400300012 (ERR-5,,,C) Half-life extrapolation 1031400300013 (ERR-6,,,F) NBS-II reference source (0.50%) 1031400300014 (ERR-7,,,F) Fissile foil masses (1.40%) 1031400300015 (ERR-8,,,C) Scattering in Pt backings 1031400300016 (ERR-9,,,C) Scattering in other structures 1031400300017 (ERR-10,,,U) Compensated beam geometry (0.57%) 1031400300018 (ERR-11,,,C) Energy spectrum (0.30%) 1031400300019 (ERR-12,,,U) Aperture diameter (0.13%) 1031400300020 (ERR-13,,,U) Deposit-aperture distance (0.14%) 1031400300021 STATUS (TABLE) Tables 7 and 8 of Ann.Nucl.Energy 5(1978)569 1031400300022 HISTORY (20020823C) Data moved from data set 10545. 1031400300023 (20170724A) On. Partial uncertainties added. 1031400300024 DATA-ERR -> ERR-T and %-uncertainties adopted for it. 1031400300025 (20171207A) On. ERR-12 and ERR-13 added. 1031400300026 ENDBIB 24 0 1031400300027 COMMON 6 3 1031400300028 ERR-6 ERR-7 ERR-10 ERR-11 ERR-12 ERR-13 1031400300029 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1031400300030 0.50 1.40 0.57 0.30 0.13 0.14 1031400300031 ENDCOMMON 3 0 1031400300032 DATA 10 4 1031400300033 EN DATA ERR-T ERR-1 ERR-2 ERR-3 1031400300034 ERR-4 ERR-5 ERR-8 ERR-9 1031400300035 KEV B PER-CENT PER-CENT PER-CENT PER-CENT 1031400300036 PER-CENT PER-CENT PER-CENT PER-CENT 1031400300037 140. 1.469 2.32 0.81 0.25 1.36 1031400300038 0.12 0.25 0.21 0.20 1031400300039 265. 1.515 2.35 1.34 0.26 0.93 1031400300040 0.11 0.25 0.20 0.23 1031400300041 770. 1.670 2.51 1.20 0.25 1.37 1031400300042 0.06 0.25 0.32 0.33 1031400300043 964. 1.643 3.05 2.07 0.26 1.42 1031400300044 0.05 0.25 0.38 0.34 1031400300045 ENDDATA 12 0 1031400300046 ENDSUBENT 45 0 1031400399999 SUBENT 10314004 20170724 14321031400400001 BIB 5 12 1031400400002 REACTION ((94-PU-239(N,F),,SIG)/(92-U-235(N,F),,SIG)) 1031400400003 COMMENT By authors: The experimental conditions were not ideal 1031400400004 for deriving cross-section ratios. 1031400400005 ERR-ANALYS (DATA-ERR) Total uncertainty. Many errors associated 1031400400006 with source yield and energy spectrum did cancel 1031400400007 resulting a final uncertainty in the ratios less than 1031400400008 the quadrature sum of the individual absolute 1031400400009 measurements. 1031400400010 STATUS (TABLE) Tables 8 of Ann.Nucl.Energy 5(1978)569 1031400400011 (DEP,10314002) 235U(n,f) cross sections 1031400400012 (DEP,10314003) 239Pu(n,f) cross sections 1031400400013 HISTORY (20170724C) On 1031400400014 ENDBIB 12 0 1031400400015 NOCOMMON 0 0 1031400400016 DATA 3 4 1031400400017 EN DATA DATA-ERR 1031400400018 KEV NO-DIM NO-DIM 1031400400019 140. 0.999 0.035 1031400400020 265. 1.189 0.037 1031400400021 770. 1.437 0.044 1031400400022 964. 1.375 0.041 1031400400023 ENDDATA 6 0 1031400400024 ENDSUBENT 23 0 1031400499999 ENDENTRY 4 0 1031499999999