ENTRY 14526 20190329 14491452600000001
SUBENT 14526001 20190329 14491452600100001
BIB 6 7 1452600100002
TITLE The Thermal-Neutron Fission Cross Section of Pu240 1452600100003
AUTHOR (C.B.Bigham) 1452600100004
REFERENCE (J,CJP,36,503,1958) 1452600100005
#doi:10.1139/p58-051 1452600100006
INSTITUTE (1CANCRC) 1452600100007
FACILITY (REAC,1CANCRC) The NRX nuclear reactor at Chalk River. 1452600100008
HISTORY (20190329C) BP 1452600100009
ENDBIB 7 0 1452600100010
COMMON 1 3 1452600100011
EN-DUMMY 1452600100012
EV 1452600100013
0.0253 1452600100014
ENDCOMMON 3 0 1452600100015
ENDSUBENT 14 0 1452600199999
SUBENT 14526002 20190329 14491452600200001
BIB 6 35 1452600200002
REACTION ((94-PU-240(N,F),,SIG,,SPA)/(94-PU-239(N,F),,SIG,,SPA))1452600200003
SAMPLE Plutonium samples 2 in. in diameter were cut from 1452600200004
large 0.016 in. aluminum sheets that had been 1452600200005
uniformly coated with several layers of lacquer 1452600200006
(cellulose nitrate dissolved in amyl acetate) 1452600200007
containing plutonium nitrate dissolved in acetone. 1452600200008
240Pu sample: 1452600200009
(94-PU-240,ENR=0.89365) 1452600200010
(94-PU-239,ENR=0.10131) 1452600200011
(94-PU-241,ENR=0.00483) 1452600200012
(94-PU-242,ENR=0.00018) 1452600200013
239Pu sample: 1452600200014
(94-PU-239,ENR=0.97884) 1452600200015
(94-PU-240,ENR=0.02043) 1452600200016
(94-PU-241,ENR=0.00073) 1452600200017
DETECTOR (FISCH) The samples were mounted on either side of a 1452600200018
thin aluminum partition in the common cathode of a 1452600200019
back-to-back gridded ion chamber. For the fission 1452600200020
counting the chamber was operated at low pressure to 1452600200021
permit complete discrimination between fission and 1452600200022
alpha pulses. 1452600200023
METHOD (RVAL,CHSEP) If isotopically pure samples of Pu239 1452600200024
and Pu240 are available, the ratio of the 1452600200025
alpha-disintegration rates and the published ratio of 1452600200026
the alpha-decay half-lives would give the ratio of 1452600200027
the masses of the samples. The ratio of the fission 1452600200028
rates in these samples, when irradiated in the same 1452600200029
neutron flux, would then give the ratio of the 1452600200030
fission cross sections. The accuracy would be limited 1452600200031
to the accuracy with which the ratio of the 1452600200032
alpha-decay half-lives is known. 1452600200033
ERR-ANALYS (DATA-ERR) Statistical errors arising from the ratio 1452600200034
measurements, decay constant ratio errors, 1452600200035
mass-spectrometer analyses. 1452600200036
STATUS (TABLE) page 506. 1452600200037
ENDBIB 35 0 1452600200038
NOCOMMON 0 0 1452600200039
DATA 2 1 1452600200040
DATA DATA-ERR 1452600200041
NO-DIM NO-DIM 1452600200042
-9.3E-04 7.7E-04 1452600200043
ENDDATA 3 0 1452600200044
ENDSUBENT 43 0 1452600299999
SUBENT 14526003 20190329 14491452600300001
BIB 5 6 1452600300002
REACTION (94-PU-240(N,F),,SIG,,SPA) 1452600300003
MONITOR (94-PU-239(N,F),,SIG,,SPA) 1452600300004
MONIT-REF ((MONIT),D.J.Hughes+,P,BNL-325,1955) 1452600300005
ERR-ANALYS (DATA-ERR) No details on sources of uncertainties. 1452600300006
STATUS (DEP,14526002) 1452600300007
(TABLE) page 506. 1452600300008
ENDBIB 6 0 1452600300009
COMMON 2 3 1452600300010
MONIT MONIT-ERR 1452600300011
B B 1452600300012
900.0 40.0 1452600300013
ENDCOMMON 3 0 1452600300014
DATA 2 1 1452600300015
DATA DATA-ERR 1452600300016
B B 1452600300017
-0.8 0.7 1452600300018
ENDDATA 3 0 1452600300019
ENDSUBENT 18 0 1452600399999
ENDENTRY 3 0 1452699999999