ENTRY 22682 20191119 22852268200000001 SUBENT 22682001 20191119 22852268200100001 BIB 9 22 2268200100002 TITLE Experimental determination of the 236U(nth,f) 2268200100003 cross section 2268200100004 AUTHOR (C.Wagemans, O.Serot, P.Geltenbort, O.Zimmer) 2268200100005 INSTITUTE (2BLGGHT) C.Wagemans 2268200100006 (2ZZZGEL) Serot 2268200100007 (2FR ILL) Geltenbort, Zimmer 2268200100008 REFERENCE (J,NSE,136,415,2000) Main Reference. Preliminary Data 2268200100009 REL-REF (M,,C.Wagemans+,J,NSE,101,293,1989) Experim. details 2268200100010 INC-SOURCE (REAC) PF1 Cold Neutron Guide 63 M Long and Curvature 2268200100011 Radius 4000 m 2268200100012 DETECTOR (SIBAR) Two 450 mm2 large and 60 microm thick 2268200100013 silicon-gold detector positioned outside the 2268200100014 collimated neutron beam. Alpha resolution is 21 keV 2268200100015 for 5.3-MeV alpha particles. 2268200100016 CORRECTION .Correction were made for the contribution of fissions 2268200100017 from other fissioning uranium isotopes present in the 2268200100018 sample. The contribution of 235U to the total count 2268200100019 rate is more than 99% 2268200100020 HISTORY (20020806C) + + Compiled by S.M. 2268200100021 (20021223A) . . Final Corrections 2268200100022 (20021223U) Last checking has been done. 2268200100023 (20191119U) SD: Ref. NSE,101,293 moved to REL-REF. 2268200100024 ENDBIB 22 0 2268200100025 NOCOMMON 0 0 2268200100026 ENDSUBENT 25 0 2268200199999 SUBENT 22682002 20021223 00002268200200001 BIB 8 36 2268200200002 REACTION (92-U-236(N,F),,SIG,,MXW) 2268200200003 FACILITY (REAC,2FR ILL) High Flux Reactor at Grenoble 2268200200004 MONITOR ((MONIT)92-U-235(N,F),,SIG,,MXW) 2268200200005 INC-SPECT .Thermal neutron spectrum with most probable energy 2268200200006 4.9 milli-eV. Neutron flux is 5.E+9 n/cm2/sec at the 2268200200007 sample position 2268200200008 SAMPLE .Samples were prepared in IRMM by electrolytic 2268200200009 deposition of uranium oxide on 0.5 mm thick Si disk. 2268200200010 236U sample thickness (131.8+-0.5) microgram/cm2. 2268200200011 234U content < 0.00001%, 235U content 0.0043+-0.0001%,2268200200012 236U content 99.9732+-0.002%, 2268200200013 238U content 0.0225+-0.0002%, 2268200200014 .For the neutron flux determination, natural uranium 2268200200015 sample was made, thickness 36.0+-0.6 microgram/cm2, 2268200200016 236U content <0.00002%, 234U content 0.0020+-0.0003%, 2268200200017 235U content 0.7209+-0.0005%, 2268200200018 238U content 99.2738+-0.0004% 2268200200019 For both samples active area has diameter 40 mm. 2268200200020 REL-REF (D,,P.F.ROSE+,R,ENDF-201,1991) ENDF/B-VI gives 47.2mb 2268200200021 Jef-2.2 gives 46.9 mb, Jendl-3.2 gives 61.3 mb 2268200200022 STATUS .From the text of main reference 2268200200023 (PRELM) By the Authors 2268200200024 ERR-ANALYS (ERR-T) Total Error is Largely Due to Uncertainty 2268200200025 In the Amount of U-235 in U-236 Sample, not Known 2268200200026 (ERR-S) Error Due to Statistical Uncertainty 2268200200027 For U-236 Sample 2268200200028 (ERR-1) Error Due to Uncertainty of Natural Uranium 2268200200029 Thickness 2268200200030 (ERR-2) Error Due to Uncertainty of U-236 Thickness 2268200200031 (ERR-3) Error Due to Uncertainty of the Key Isotopes 2268200200032 Evaluated by Compiler 2268200200033 (ERR-4) Error Due to Normalization 2268200200034 (ERR-5) Error Due to Uncertaity of Westcott Factor 2268200200035 (ERR-6) Error Due to Neutron Flux Uncertainty 2268200200036 (MONIT-ERR) Error of the 235U(N,F) Reference Cross 2268200200037 Section 2268200200038 ENDBIB 36 0 2268200200039 COMMON 10 6 2268200200040 EN-NRM MONIT MONIT-ERR ERR-S ERR-1 ERR-2 2268200200041 ERR-3 ERR-4 ERR-5 ERR-6 2268200200042 EV B B PER-CENT PER-CENT PER-CENT 2268200200043 PER-CENT PER-CENT PER-CENT PER-CENT 2268200200044 0.0253 584.25 1.1 0.3 1.7 0.42268200200045 0.2 1. 0.1 0.1 2268200200046 ENDCOMMON 6 0 2268200200047 DATA 4 2 2268200200048 EN-MEAN DATA ERR-T DATA-MAX 2268200200049 MILLI-EV MB MB MB 2268200200050 4.9 0.3 1. 2268200200051 4.9 1.3 2268200200052 ENDDATA 4 0 2268200200053 ENDSUBENT 52 0 2268200299999 SUBENT 22682003 20021223 00002268200300001 BIB 5 10 2268200300002 REACTION (92-U-236(N,F),,SIG,,MXW,DERIV) Derived from Resonance 2268200300003 Parameters Given in (REL-REF-2) Taking Into Account 2268200300004 Data Obtained in the Article 2268200300005 ANALYSIS .Breit-Wigner formula 2268200300006 ASSUMED (ASSUM,92-U-236(N,F),,WID) For 5.45 eV Resonance 2268200300007 REL-REF (R,,G.JAMES+,R,AERE-M-2082,1968) 2268200300008 (R,13642004,W.PARKER+,J,PR/C,49,672,1994) 2268200300009 STATUS .Data from the Text of Main Reference 2268200300010 (DEP,22682002) 2268200300011 (COREL,13642001) 2268200300012 ENDBIB 10 0 2268200300013 NOCOMMON 0 0 2268200300014 DATA 4 1 2268200300015 EN-MEAN DATA ASSUM ASSUM-ERR 2268200300016 MILLI-EV MB MILLI-EV MILLI-EV 2268200300017 4.9 0.17 0.0013 0.0001 2268200300018 ENDDATA 3 0 2268200300019 ENDSUBENT 18 0 2268200399999 ENDENTRY 3 0 2268299999999