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