ENTRY 41513 20080422 41434151300000001 SUBENT 41513001 20080422 41434151300100001 BIB 15 27 4151300100002 TITLE The 234-U neutron induced fission cross-section near 4151300100003 the thermal point. 4151300100004 AUTHOR (M.Florek, V.Yu.Konovalov, L.B.Pikelner,Yu.S.Zamyatnin,4151300100005 Sh.S.Zeinalov) 4151300100006 INSTITUTE (4ZZZDUB) V.Yu.Konovalov, L.B.Pikelner, Yu.S.Zamyatnin,4151300100007 Sh.S.Zeinalov 4151300100008 (3SLKUB) M.Florek 4151300100009 REFERENCE (W,Konovalov,20080429) Main reference. 4151300100010 FACILITY (REAC,4ZZZDUB) IBR-2 pulsed reactor. 4151300100011 INC-SOURCE (REAC) 4151300100012 INC-SPECT Tangential neutron beam 4151300100013 METHOD (TOF) 4151300100014 Background was measured with 0.5mm thick cadmium filter4151300100015 in the neutron beam. Measurement time for spectrum 4151300100016 without filter - 33 h, and background one - 13 h. 4151300100017 PART-DET (FF) 4151300100018 DETECTOR (IOCH) Multisectional ionization chamber containing: 4151300100019 SAMPLE 12.5 mg of 234-U and 0.84 mg of 235-U used for neutron 4151300100020 flux determination and energy calibration. 4151300100021 235-U content 0.078+-0.001% in the 234U sample. 4151300100022 ANALYSIS Contribution of 235-U was calculated using 235-U TOF 4151300100023 spectra normalized on samples mass ratio, ratio of the 4151300100024 average reactor power during both measurements and 4151300100025 content of 235U in the 234U sample. 4151300100026 STATUS (TABLE) Data received from author V.Yu.Konovalov. 4151300100027 ERR-ANALYS (DATA-ERR) Errors are not specified. 4151300100028 HISTORY (20080429C) Compiled at CJD. M.M. 4151300100029 ENDBIB 27 0 4151300100030 NOCOMMON 0 0 4151300100031 ENDSUBENT 30 0 4151300199999 SUBENT 41513002 20080429 41434151300200001 BIB 1 1 4151300200002 REACTION (92-U-234(N,F),,SIG) 4151300200003 ENDBIB 1 0 4151300200004 NOCOMMON 0 0 4151300200005 DATA 3 19 4151300200006 EN DATA DATA-ERR 4151300200007 EV B B 4151300200008 0.007 0.748458459 .080406301 4151300200009 0.012 0.451590841 .051771049 4151300200010 0.017 0.36453046 .042449596 4151300200011 0.022 0.287805376 .03620512 4151300200012 0.027 0.223271837 .031406166 4151300200013 0.032 0.202746409 .028824836 4151300200014 0.037 0.165143594 .026205377 4151300200015 0.042 0.149088677 .024437472 4151300200016 0.047 0.136164506 .022983146 4151300200017 0.053 0.129120555 .02172448 4151300200018 0.058 0.107994371 .020505552 4151300200019 0.062 0.100517237 .01967837 4151300200020 0.067 0.100947817 .019043802 4151300200021 0.074 0.099268471 .018396389 4151300200022 0.078 0.095246502 .017874519 4151300200023 0.083 0.094816301 .017578072 4151300200024 0.088 0.086042647 .016985248 4151300200025 0.094 0.086448188 .016604089 4151300200026 0.098 0.08591673 .016040014 4151300200027 ENDDATA 21 0 4151300200028 ENDSUBENT 27 0 4151300299999 SUBENT 41513003 20080429 41434151300300001 BIB 3 7 4151300300002 REACTION 1(92-U-234(N,0),,EN) Resonance energy 4151300300003 2((92-U-234(N,EL),,WID,,G)*(92-U-234(N,F),,WID)) 4151300300004 g*Gn*Gf upper estimation. 4151300300005 ANALYSIS Experimental points was fitted by Breit-Wigner formula 4151300300006 in order to estimate the parameters of the negative 4151300300007 resonance that caused deviation from 1/v law. 4151300300008 STATUS (DEP,41513002) 4151300300009 ENDBIB 7 0 4151300300010 NOCOMMON 0 0 4151300300011 DATA 2 1 4151300300012 DATA 1DATA-MAX 2 4151300300013 EV EV-SQ 4151300300014 -0.003 6.E-12 4151300300015 ENDDATA 3 0 4151300300016 ENDSUBENT 15 0 4151300399999 SUBENT 41513004 20080429 41434151300400001 BIB 4 7 4151300400002 REACTION (92-U-234(N,EL),,WID,,,DERIV) 4151300400003 ASSUMED (ASSUM,92-U-234(N,F),,WID,,AV) 4151300400004 ANALYSIS Using average fission width for 234-U resonance 4151300400005 ~10 eV , neutron width of the negative resonance 4151300400006 Gn~10-7-10-8 eV was obtained. 4151300400007 It could be p-wave resonance. 4151300400008 STATUS (DEP,41513003) 4151300400009 ENDBIB 7 0 4151300400010 COMMON 1 3 4151300400011 ASSUM 4151300400012 EV 4151300400013 1.E-05 4151300400014 ENDCOMMON 3 0 4151300400015 DATA 2 1 4151300400016 EN-RES DATA-MAX 4151300400017 EV EV 4151300400018 -0.003 1.E-07 4151300400019 ENDDATA 3 0 4151300400020 ENDSUBENT 19 0 4151300499999 ENDENTRY 4 0 4151399999999