ENTRY 22492 20090828 22182249200000001 SUBENT 22492001 20090828 22182249200100001 BIB 14 43 2249200100002 TITLE .Experimental Determination of the 234U(N-th,F) 2249200100003 Cross Section 2249200100004 AUTHOR (C.Wagemans, J.Wagemans, P.Geltenbort, O.Zimmer, 2249200100005 O.Serot) 2249200100006 INSTITUTE (2BLGGHT) C.Wagemans 2249200100007 (2ZZZGEL) J.Wagemans 2249200100008 (2FR ILL) Geltenbort, Zimmer 2249200100009 (2FR CAD) Serot 2249200100010 REFERENCE (J,NSE,141,171,2002) Main reference. Corrected data 2249200100011 (J,NSE,132,308,1999) Preliminary Data 2249200100012 REL-REF (M,23082001,J.Heyse+,J,NSE,156,211,2007) Sample 234U 2249200100013 content correction 2249200100014 FACILITY (REAC,2FR ILL) High flux reactor at Grenoble 2249200100015 INC-SOURCE (REAC) PF1 cold neutron guide 63 m long and curvature 2249200100016 Radius 4000 M 2249200100017 DETECTOR (SIBAR) Two 600 mm-sq large and 100 micrometer thick 2249200100018 silicium-gold detector positioned outside the 2249200100019 collimated neutron beam. Alpha resolution is 21 keV 2249200100020 at 5.3-MeV alpha particles 2249200100021 PART-DET (FF,A) 2249200100022 MONITOR (92-U-235(N,F),,SIG) 2249200100023 SAMPLE .Natural U sample for the neutron flux determination, 2249200100024 by U-235(n,f) cross section. Uranium thickness is 2249200100025 36.0+-0.6 microgram/cm2, active diameter is 40 mm, 2249200100026 U-234 content is 0.0020%, U-235 content is 0.7209%, 2249200100027 U-236 content is <2.E-5%, U-238 content is 99.2738% 2249200100028 CORRECTION .Correction were made for the contribution of fissions 2249200100029 from other fissioning uranium isotopes present in the 2249200100030 sampleS 234U and 238U, for scattering in silicon 2249200100031 backing. 2249200100032 ERR-ANALYS (ERR-T) Total error. 2249200100033 (ERR-1) Error of the natural uranium sample thickness 2249200100034 (ERR-2) Error of the 234-U sample thickness 2249200100035 (ERR-3) Error of 235U content in 234U sample - main 2249200100036 contribution to the total error 2249200100037 (ERR-4) Error of normalization of the 234U and 2249200100038 natural uranium counting rate 2249200100039 (ERR-5) Error of the Westcott factor 2249200100040 (MONIT-ERR) Error of the 235U(N,F) cross section 2249200100041 HISTORY (20001113C) + + Compiled by S.M. 2249200100042 (20020804A) + + Correction made by S.M. 2249200100043 (20090828A) Reference added. BIB information 2249200100044 corrected - S.M. 2249200100045 ENDBIB 43 0 2249200100046 COMMON 7 6 2249200100047 MONIT MONIT-ERR ERR-1 ERR-2 ERR-3 ERR-4 2249200100048 ERR-5 2249200100049 B B PER-CENT PER-CENT PER-CENT PER-CENT 2249200100050 PER-CENT 2249200100051 584.25 1.1 1.7 1. 1.3 1. 2249200100052 0.1 2249200100053 ENDCOMMON 6 0 2249200100054 ENDSUBENT 53 0 2249200199999 SUBENT 22492002 20020805 00002249200200001 BIB 5 19 2249200200002 REACTION (92-U-234(N,F),,SIG,,MXW) 2249200200003 INC-SPECT .Thermal neutron spectrum with mean energy 11 milli-eV,2249200200004 (11 MeV in the article), neutron flux 5.E+9 n/cm2/sec 2249200200005 at the sample position 2249200200006 SAMPLE .Two samples were prepared by electrolytic deposition 2249200200007 of uranium oxide on 0.5 mm thick Si disk. 2249200200008 =Natural U sample for the neutron flux determination, 2249200200009 uranium thickness 36.0+-0.6 microgram/cm2, active 2249200200010 area has diameter 40 mm, 2249200200011 U-234 content is 0.0020%, U-235 content is 0.7209%, 2249200200012 U-236 content is <2.E-5%, U-238 content is 99.2738% 2249200200013 =Enriched 234U sample with exactly the same geometry, 2249200200014 234U thickness 96.5+-1 microgram/cm2, 2249200200015 U-233 content is 0.001%, U-234 content is 99.868%, 2249200200016 U-235 content is 0.076%, U-236 content is 0.048%, 2249200200017 U-238 content is 0.007% 2249200200018 REL-REF (A,,G.JAMES+,J,PR/C,15,2083,1977) 2249200200019 STATUS .From the Text of Main Reference 2249200200020 (SPSDD,22492003) 2249200200021 ENDBIB 19 0 2249200200022 NOCOMMON 0 0 2249200200023 DATA 3 1 2249200200024 EN-MEAN DATA ERR-T 2249200200025 MILLI-EV MB MB 2249200200026 11. 300. 20. 2249200200027 ENDDATA 3 0 2249200200028 ENDSUBENT 27 0 2249200299999 SUBENT 22492003 20090828 22182249200300001 BIB 6 18 2249200300002 REACTION (92-U-234(N,F),,SIG,,MXW) 2249200300003 INC-SPECT .Thermal neutron spectrum with mean energy 11 milli-eV,2249200300004 (11 MeV in the article), neutron flux 5.E+9 n/cm2/sec 2249200300005 at the sample position 2249200300006 SAMPLE .Revised sample content determination based on new 2249200300007 alpha-particle analysis of the 234U sample. 2249200300008 .The 234U sample was prepared by electrolytic depo- 2249200300009 sition of uranium oxide on 0.5 mm thick Si disk. 2249200300010 Thickness (137+-1) microgram/cm2, 40% more than in 2249200300011 in previous analysis, NSE,132.308,2000. Active diam. 2249200300012 40 mm, isotopic content is: 2249200300013 U-233 0.001%, U-234 99.868%, U-235 (0.076+-0.001)%, 2249200300014 U-236 0.048%, U-238 007%. 2249200300015 REL-REF (A,10620001,G.James+,J,PR/C,15,2083,1977) 2249200300016 STATUS (TABLE) From the text of NSE,141,171,2002, page 172 2249200300017 (APRVD) By the Authors in the text in NSE,141,171 2249200300018 and confirmed in NSE,156,211,2007 2249200300019 HISTORY (20090828U) BIB information corrected and updated 2249200300020 ENDBIB 18 0 2249200300021 NOCOMMON 0 0 2249200300022 DATA 3 1 2249200300023 EN-MEAN DATA ERR-T 2249200300024 MILLI-EV MB MB 2249200300025 11. 67. 14. 2249200300026 ENDDATA 3 0 2249200300027 ENDSUBENT 26 0 2249200399999 ENDENTRY 3 0 2249299999999