ENTRY 41024 20141201 41664102400000001 SUBENT 41024001 20141201 41664102400100001 BIB 12 36 4102400100002 TITLE Cross-section of the U-238(N,2N)U-237 reaction induced 4102400100003 by neutrons from Cf-252 spontaneous fission 4102400100004 AUTHOR (M.V.Blinov,E.A.Gromova,S.S.Kovalenko,B.D.Stsiborskii, 4102400100005 S.V.Chuvaev,B.M.Shiryaev) 4102400100006 INSTITUTE (4RUSRI) 4102400100007 REFERENCE (J,AE,65,(3),206,1988) Data are given 4102400100008 (J,SJA,65,761,1988) Engl.translation of AE,65,(3),206 4102400100009 METHOD (ACTIV) Activation. 4102400100010 Measurement of induced activity was started a day 4102400100011 after the end of radiation. 4102400100012 (CHSEP) Measurement also was done after radiochemical 4102400100013 purification of the irradiated sample from fragment 4102400100014 elements and transuranium elements. 4102400100015 DETECTOR (GELI) For activation measurement . 4102400100016 Calibrated by Ra-226 gamma sources. 4102400100017 (FISCH) For neutron flux measurements . 4102400100018 With U-238-F(4) thin layer. 4102400100019 MONITOR ((MONIT1)92-U-238(N,F),,SIG) 4102400100020 ((MONIT2)13-AL-27(N,A)11-NA-24,,SIG) 4102400100021 DECAY-MON (11-NA-24,,DG,1368.5,0.99997) 4102400100022 INC-SOURCE (CF252) Cf-252 spontaneous fission sources: 4102400100023 -two neutron sources of about 9 microg each at 4102400100024 distance 2 cm; 4102400100025 -three sources of overall mass about 50 microg. 4102400100026 SAMPLE Oxide U3-O8, powder in aluminum boxes, weight 2.5 4102400100027 gram, U-238 content is 99.999 percent 4102400100028 ERR-ANALYS (ERR-1) Error due to the detector efficiency and 4102400100029 neutron flux density, 4102400100030 (ERR-2) Error in correction due differences in the 4102400100031 sample dimensions and calibration sources; 4102400100032 (ERR-3) Error in the correction for self-absorption; 4102400100033 (ERR-4) Error due to the monitor errors 4102400100034 HISTORY (19901025C) + + Compiled at the centre - CJD + + 4102400100035 (19910201A) Codes in SF1, SF4 corrected 4102400100036 (20141229A) M.M. Subent 002 reaction was corrected. 4102400100037 SJA,65,761,1988 was added. BIB information was updated.4102400100038 ENDBIB 36 0 4102400100039 COMMON 5 3 4102400100040 KT-DUMMY MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 4102400100041 MEV MB PER-CENT MB PER-CENT 4102400100042 1.42 317. 2. 1.01 2. 4102400100043 ENDCOMMON 3 0 4102400100044 ENDSUBENT 43 0 4102400199999 SUBENT 41024002 20141201 41664102400200001 BIB 6 11 4102400200002 REACTION (92-U-238(N,2N)92-U-237,,SIG,,FIS) 4102400200003 DECAY-DATA (92-U-237,6.75D,DG,208.,0.224) 4102400200004 CORRECTION For self-absorption of radiation by the sample, 4102400200005 the absolute yield of gamma rays, pulse pileus, dead 4102400200006 time of the analyzer, for geometric and other factors. 4102400200007 REL-REF (D,,G.Shani,J,ANE,10,(9),473,1983) 12.2+-1.5 mb. 4102400200008 STATUS (TABLE) Text, page 207, of J,AE,65,(3),206,1988. 4102400200009 (COREL,40996002) Previously published in 4102400200010 C,87KIEV,3,277,1987; data are the same. 4102400200011 HISTORY (19910201A) Code U-237 to U-238 changed 4102400200012 (20141229A) M.M. FIS code was added in REACTION. 4102400200013 ENDBIB 11 0 4102400200014 NOCOMMON 0 0 4102400200015 DATA 6 1 4102400200016 DATA ERR-T ERR-1 ERR-2 ERR-3 ERR-4 4102400200017 MB MB PER-CENT PER-CENT PER-CENT PER-CENT 4102400200018 19.2 1.9 5. 4.5 3. 2. 4102400200019 ENDDATA 3 0 4102400200020 ENDSUBENT 19 0 4102400299999 ENDENTRY 2 0 4102499999999