ENTRY 21943 20090315 22082194300000001 SUBENT 21943001 20090315 22082194300100001 BIB 15 43 2194300100002 INSTITUTE (2BLGGHT) P.D'H. 2194300100003 (2BLGMOL) C.W. 2194300100004 (2FR LYO) A.E. 2194300100005 (2FR ILL) R.B. Experimental site 2194300100006 REFERENCE (J,ANE,11,(10),485,1984) 2194300100007 AUTHOR (P.D'Hondt,C.Wagemans,A.Emsallem,R.Brissot) 2194300100008 TITLE -Measurement of the thermal-neutron induced fission 2194300100009 cross-section of U-238 2194300100010 FACILITY (REAC,2FR ILL) Thermal N-guide of high-flux reactor 2194300100011 INC-SOURCE (REAC) .1 percent fast-N in thermal N-beam 2194300100012 epith+fast-N/Th about e+06 2194300100013 .At the end of 87 m N-guide ,flux about 5e+08 2194300100014 N/cm**2/sec 2194300100015 value determined by a 31 micro-g/cm**2 natural2194300100016 U-target(0.711 percent U-235) 2194300100017 .Max of mxw distribution at 50 milli-eV 2194300100018 INC-SPECT .Thermal reactor spectrum. 2194300100019 SAMPLE .Target at 30 degree/beam axis 2194300100020 .Prepared at the mass-separator of the ipn-lyon 2194300100021 -first enriched sample U-238 on 10 micro-m Al 2194300100022 thickness=40 micro-g/cm**2 2194300100023 0.17 ppm U-235 2194300100024 irradiation time 308 hr 2194300100025 -second sample on 300 micro-m Si 2194300100026 thickness=20 micro-g/cm**2 2194300100027 0.012 ppm U-235 2194300100028 irradiation time 374 hr 2194300100029 DETECTOR (SOLST) .Au-Si surface barrier detector to detect 2194300100030 fission fragments 2194300100031 .Area=450 mm**2 2194300100032 MONITOR (92-U-235(N,F),,SIG) 2194300100033 ADD-RES .Negative resonance contributing with about 8 micro-B 2194300100034 to the thermal fission cross-section is found 2194300100035 STATUS .Main reference in the text 2194300100036 HISTORY (19850124C) Bl 2194300100037 (19850423E) 2194300100038 (20090315U) Last checking has been done. 2194300100039 CORRECTION .On mass determination and small geometry differences 2194300100040 are eliminated 2194300100041 .U-235 contribution in (N,F) reaction 2194300100042 .Pu-239 contribution in (N,g) reaction + 2 decrease B- 2194300100043 about 1 micro-B 2194300100044 ERR-ANALYS (ERR-T) Total error 2194300100045 ENDBIB 43 0 2194300100046 COMMON 1 3 2194300100047 EN-DUMMY 2194300100048 EV 2194300100049 2.53E-02 2194300100050 ENDCOMMON 3 0 2194300100051 ENDSUBENT 50 0 2194300199999 SUBENT 21943002 19850423 00002194300200001 BIB 3 4 2194300200002 REACTION (92-U-238(N,F),,SIG,,MXW) 2194300200003 STATUS .MAIN REFERENCE IN THE TEXT 2194300200004 HISTORY (850124C) 2194300200005 (850423E) 2194300200006 ENDBIB 4 0 2194300200007 NOCOMMON 0 0 2194300200008 DATA 4 1 2194300200009 DATA ERR-T MONIT MONIT-ERR 2194300200010 MICRO-B MICRO-B B B 2194300200011 1.1000E+01 2.0000E+00 5.8760E+02 2.6000E+00 2194300200012 ENDDATA 3 0 2194300200013 ENDSUBENT 12 0 2194300299999 ENDENTRY 2 0 2194399999999