ENTRY 22024 20130402 22362202400000001 SUBENT 22024001 20130402 22362202400100001 BIB 15 59 2202400100002 TITLE Measurement of fission cross section ratios of U-236, 2202400100003 Np-237 and Am-243 relative to U-235 from 0.7 to 7 MeV2202400100004 AUTHOR (K.Kanda, T.Iwasaki, M.Terayama, Y.Karino, M.Baba, 2202400100005 N.Hirakawa) 2202400100006 INSTITUTE (2JPNTOH) 2202400100007 REFERENCE ((P,INDC(JPN)-108,99,1986)=(P,NEANDC(J)-122,1986)) 2202400100008 (P,NETU-47,1986) 2202400100009 FACILITY (DYNAM,2JPNTOH) 4.5 MV Dynamitron 2202400100010 INC-SOURCE Continuous beams were used, except in the case of 2202400100011 Am-243, where pulsed neutrons were used in order to 2202400100012 reduce the uncertainty caused by subtracting the 2202400100013 spontaneous fission counts of the impurity Cm-244. 2202400100014 (P-T) Reaction with absorbed tritium-titanium targets 2202400100015 were used to produce neutrons in the energy range 2202400100016 0.7 - 3 MeV. 2202400100017 (D-D) Reaction with a deuterium gas target was used 2202400100018 to produce neutrons in the energy range 4.2 - 7 MeV. 2202400100019 INC-SPECT Source neutron spectra were measured with tof by using 2202400100020 a NE213 scintillation detector, placed at a distance 2202400100021 of 14 m from the target in the 0 degree direction. 2202400100022 Mean neutron energies and spreads at the sample 2202400100023 position were then calculated by a Monte Carlo method.2202400100024 DETECTOR (FISCH) A fission chamber of the parallel plate 2202400100025 ionization type was used. 2202400100026 The U-235 sample and another sample were mounted back 2202400100027 to back in the chamber 2 cm from the collector 2202400100028 electrode. 2202400100029 PART-DET (FF) 2202400100030 MONITOR (92-U-235(N,F),,SIG) 2202400100031 SAMPLE The sample materials were electrodeposited on 36 mm 2202400100032 diameter by 0.3 or 0.4 mm thick platinum plates. 2202400100033 The diameter of deposition was 25 mm. 2202400100034 Isotopic composition and number of atoms were 2202400100035 determined by measuring the alpha spectrum and 2202400100036 activity. 2202400100037 Details of the samples are given in Table 1 of NETU-47.2202400100038 During irradiations, the samples were placed 2202400100039 perpendicular to the beam at a distance of 5 to 10 cm 2202400100040 from the target. 2202400100041 CORRECTION The cross section ratios were corrected for events 2202400100042 caused by room-scattered neutrons. 2202400100043 Corrections due to the pulse-height discrimination 2202400100044 were made by extrapolating to zero pulse-height, 2202400100045 using a Gaussian function. 2202400100046 Corrections were also applied for self-absorption of 2202400100047 fission fragments in the samples, as well as for 2202400100048 fission induced by low energy neutrons. 2202400100049 Contributions from impurities in the samples, 2202400100050 especially the spontaneous fission of Cm-244 present 2202400100051 in the Am-243 sample, were also corrected for. 2202400100052 ERR-ANALYS (DATA-ERR) Errors on cross section ratios were 2202400100053 determined in a covariance analysis of the 2202400100054 experimental data. 2202400100055 STATUS Data were taken from NETU-47,1986. 2202400100056 HISTORY (19861113C) NO. 2202400100057 (19861212E) 2202400100058 (19870825U) IF. 2202400100059 (19870827E) 2202400100060 (20130402D) On. 004 deleted. Same data in 22044.002. 2202400100061 ENDBIB 59 0 2202400100062 NOCOMMON 0 0 2202400100063 ENDSUBENT 62 0 2202400199999 SUBENT 22024002 19881117 00002202400200001 BIB 3 6 2202400200002 REACTION ((92-U-236(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2202400200003 STATUS .DATA WERE TAKEN FROM PRIVATE COMMUNICATION. 2202400200004 HISTORY (861113C) NO. 2202400200005 (861212E) 2202400200006 (870825U) IF. 2202400200007 (870827E) 2202400200008 ENDBIB 6 0 2202400200009 NOCOMMON 0 0 2202400200010 DATA 4 27 2202400200011 EN EN-RSL DATA DATA-ERR 2202400200012 MEV MEV NO-DIM PER-CENT 2202400200013 9.9000E-01 2.5000E-01 3.2140E-01 1.6000E+00 2202400200014 1.0800E+00 2.3000E-01 3.8130E-01 1.5000E+00 2202400200015 1.1900E+00 2.1000E-01 5.0690E-01 1.4000E+00 2202400200016 1.2800E+00 2.3000E-01 5.7240E-01 1.3000E+00 2202400200017 1.3900E+00 2.1000E-01 6.0090E-01 1.3000E+00 2202400200018 1.4800E+00 2.0000E-01 5.8790E-01 1.3000E+00 2202400200019 1.5900E+00 2.0000E-01 5.7080E-01 1.3000E+00 2202400200020 1.7800E+00 1.9000E-01 6.3310E-01 1.3000E+00 2202400200021 1.9800E+00 1.8000E-01 6.8170E-01 1.3000E+00 2202400200022 2.1600E+00 1.8000E-01 6.9680E-01 1.3000E+00 2202400200023 2.3900E+00 1.8000E-01 7.1780E-01 1.3000E+00 2202400200024 2.5800E+00 1.7000E-01 7.0630E-01 1.7000E+00 2202400200025 2.5900E+00 4.9000E-01 6.8310E-01 1.1000E+00 2202400200026 2.7800E+00 4.1000E-01 6.9670E-01 1.1000E+00 2202400200027 2.8500E+00 1.7000E-01 6.9590E-01 1.6000E+00 2202400200028 2.9900E+00 4.2000E-01 6.9350E-01 1.1000E+00 2202400200029 4.1900E+00 6.0000E-01 7.8630E-01 1.1000E+00 2202400200030 4.7600E+00 4.2000E-01 7.8870E-01 1.1000E+00 2202400200031 5.1500E+00 3.6000E-01 8.0120E-01 1.1000E+00 2202400200032 5.4000E+00 3.0000E-01 8.1110E-01 1.1000E+00 2202400200033 5.7100E+00 2.8000E-01 8.4150E-01 1.1000E+00 2202400200034 5.9600E+00 1.8000E-01 8.4500E-01 1.1000E+00 2202400200035 6.2400E+00 1.4000E-01 8.6250E-01 1.3000E+00 2202400200036 6.4800E+00 1.4000E-01 8.8340E-01 1.3000E+00 2202400200037 6.7400E+00 1.0000E-01 9.1490E-01 1.3000E+00 2202400200038 6.9800E+00 1.8000E-01 9.4400E-01 1.3000E+00 2202400200039 6.9900E+00 1.6000E-01 9.3480E-01 1.3000E+00 2202400200040 ENDDATA 29 0 2202400200041 ENDSUBENT 40 0 2202400299999 SUBENT 22024003 19881117 00002202400300001 BIB 3 6 2202400300002 REACTION ((93-NP-237(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2202400300003 STATUS .DATA WERE TAKEN FROM PRIVATE COMMUNICATION. 2202400300004 HISTORY (861113C) NO. 2202400300005 (861212E) 2202400300006 (870825U) IF. 2202400300007 (870827E) 2202400300008 ENDBIB 6 0 2202400300009 NOCOMMON 0 0 2202400300010 DATA 4 21 2202400300011 EN EN-RSL DATA DATA-ERR 2202400300012 MEV MEV NO-DIM PER-CENT 2202400300013 7.0000E-01 2.5000E-01 9.5200E-01 1.1000E+00 2202400300014 9.8000E-01 2.4000E-01 1.1970E+00 1.1000E+00 2202400300015 1.2000E+00 2.3000E-01 1.2270E+00 1.1000E+00 2202400300016 1.4400E+00 2.0000E-01 1.2980E+00 1.1000E+00 2202400300017 1.6700E+00 2.0000E-01 1.3320E+00 1.1000E+00 2202400300018 1.9000E+00 1.7000E-01 1.3290E+00 1.1000E+00 2202400300019 2.1400E+00 1.9000E-01 1.3400E+00 1.1000E+00 2202400300020 2.3800E+00 1.8000E-01 1.3410E+00 1.1000E+00 2202400300021 2.5900E+00 4.9000E-01 1.3750E+00 1.1000E+00 2202400300022 2.7800E+00 4.1000E-01 1.3820E+00 1.1000E+00 2202400300023 2.9900E+00 4.2000E-01 1.3810E+00 1.1000E+00 2202400300024 4.1900E+00 6.0000E-01 1.4250E+00 1.1000E+00 2202400300025 4.7600E+00 4.2000E-01 1.4500E+00 1.1000E+00 2202400300026 5.1100E+00 3.4000E-01 1.4080E+00 1.0000E+00 2202400300027 5.4000E+00 3.2000E-01 1.4300E+00 1.1000E+00 2202400300028 5.6900E+00 2.8000E-01 1.4870E+00 1.0000E+00 2202400300029 5.9700E+00 1.4000E-01 1.5220E+00 1.1000E+00 2202400300030 6.1800E+00 2.0000E-01 1.5670E+00 1.1000E+00 2202400300031 6.4100E+00 1.6000E-01 1.5070E+00 1.1000E+00 2202400300032 6.6800E+00 1.6000E-01 1.4760E+00 1.1000E+00 2202400300033 6.9900E+00 1.6000E-01 1.4320E+00 1.1000E+00 2202400300034 ENDDATA 23 0 2202400300035 ENDSUBENT 34 0 2202400399999 NOSUBENT 22024004 20130402 22362202400400001 ENDENTRY 4 0 2202499999999