ENTRY 13371 20180312 1337100000001
SUBENT 13371001 20180312 20180726 1337100100001
BIB 11 39 1337100100002
TITLE Yield of Xe133 in the Thermal Neutron Fission of U235 1337100100003
AUTHOR (S.Katcoff,W.Rubinson) 1337100100004
REFERENCE (J,PR,91,1458,1953) 1337100100005
#doi:10.1103/PhysRev.91.1458 1337100100006
INSTITUTE (1USABNL) 1337100100007
FACILITY (REAC,1USABNL) Brookhaven pile. 1337100100008
INC-SPECT A constant (+-2%) flux of ~2x10**11 neutrons/cm2/sec. 1337100100009
SAMPLE (92-U-235,ENR=0.9372) Five fission foils, each 1337100100010
containing 7.855x10**-3 microg of 93.72 percent U235, 1337100100011
were prepared by the standard method. Two additional 1337100100012
foils were prepared by slight variations of this 1337100100013
method: one, without final ignition, to test whether 1337100100014
ignition affects the escape of fission recoils; and the1337100100015
other, by stippling the foil solution and rinse in 1337100100016
small droplets over the surface of the Pt before 1337100100017
evaporation and ignition, to test whether possible 1337100100018
clumping of the U was great enough to cause loss of 1337100100019
fission recoils. 1337100100020
DETECTOR (PROPC,FISCH) The gas counters were of glass, 2 cm in 1337100100021
diameter and 30 cm long, with chemically deposited 1337100100022
silver cathodes whose volumes had been measured to 1337100100023
within 0.2 percent. 1337100100024
METHOD (CHSEP,INTB) Two slug solutions were prepared 1337100100025
independently of each other by diluting aliquots of 1337100100026
the U235 stock solution. The slug was bombarded in 1337100100027
the space between the two fission foils for an hour. 1337100100028
The total of the recorded fissions of each foil was 1337100100029
then corrected for background and counting-rate loss, 1337100100030
divided by 60 to give the foil fission rate as 1337100100031
fissions per min, and multiplied by the ratio of 1337100100032
slug weight to foil weight to give the slug fission 1337100100033
rate. 1337100100034
COMMENT Surprisingly, modern T1/2 values for 133Xe and 135Xe 1337100100035
are 5.2475 d and 9.14 h, respectively. Almost no 1337100100036
changes in the last 65 years. 1337100100037
HISTORY (19891211C) VM 1337100100038
(20180312A) BP: Updated to new date formats,lower case.1337100100039
corrections according last EXFOR rules and Dict., 1337100100040
added doi and minor updates. 1337100100041
ENDBIB 39 0 1337100100042
COMMON 1 3 1337100100043
EN-DUMMY 1337100100044
EV 1337100100045
0.0253 1337100100046
ENDCOMMON 3 0 1337100100047
ENDSUBENT 46 0 1337100199999
SUBENT 13371002 20180312 20180726 1337100200001
BIB 6 19 1337100200002
REACTION ((92-U-235(N,F)ELEM/MASS,IND,FY,,MXW)/ 1337100200003
(92-U-235(N,F)MASS,CHN,FY)) 1337100200004
METHOD (RELFY) In our experimental procedure two identical 1337100200005
uranium samples(~40 microg U235 in each) were sealed 1337100200006
into the usual quartz cells and then irradiated side 1337100200007
by side in one of the pile pneumatic tubes for 0.033 1337100200008
hr. The slugs were dissolved and swept with Xe 1337100200009
carrier and 2 l of helium as rapidly as possible. The 1337100200010
Xe of extract a collected at the bottom of the 1337100200011
charcoal column was probably contaminated with some 1337100200012
short-lived Kr isotopes. Therefore the first 10-15 1337100200013
percent of the Xe desorbed from the column was 1337100200014
discarded. The remainder was collected and put into 1337100200015
counters in the usual manner. 1337100200016
ERR-ANALYS (DATA-ERR) No details on sources of uncertainties. 1337100200017
RESULT (FRIND) 1337100200018
DECAY-DATA ((1.)54-XE-133-G,5.27D) 1337100200019
((2.)54-XE-135-G,9.15HR) 1337100200020
STATUS (TABLE) Abstract and page 1467. 1337100200021
ENDBIB 19 0 1337100200022
NOCOMMON 0 0 1337100200023
DATA 6 2 1337100200024
MASS ELEMENT DATA DATA-ERR DATA-MAX DECAY-FLAG 1337100200025
NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 1337100200026
133. 54. 0.001 1.1337100200027
135. 54. 0.035 0.010 2.1337100200028
ENDDATA 4 0 1337100200029
ENDSUBENT 28 0 1337100299999
SUBENT 13371003 20180312 20180726 1337100300001
BIB 6 20 1337100300002
REACTION (92-U-235(N,F)54-XE-133,CUM,FY,,MXW) 1337100300003
METHOD (BSPEC) The Xe from each run was measured into two 1337100300004
counters, designated a and b, each of which was 1337100300005
counted ten times, over a period of two weeks, 1337100300006
starting about 10 days after irradiation, on each of 1337100300007
two electronic circuits, designated 1 and 2. Eight 1337100300008
different counters were used for the five runs. 1337100300009
ANALYSIS The basic Xe activity datum that enters the fission 1337100300010
yield calculation in a given run is the mean of the 1337100300011
corrected a and b averages of that run. This gives 1337100300012
the disintegration rate of the total Xe in the given 1337100300013
slug 253 hr after the end of a 1-hr bombardment. Of 1337100300014
this total activity, about 98.8 percent was 5.27-day 1337100300015
Xe133, one percent was 2.3-day Xe133m, and the 1337100300016
remaining 0.2 percent was 12.0-day Xe131m. 1337100300017
ERR-ANALYS (DATA-ERR) Probable error. 1337100300018
(ERR-1) 1% Slug fission rate. 1337100300019
(ERR-2) 2% Xe disintegration rates. 1337100300020
DECAY-DATA (54-XE-133-G,5.27D) 1337100300021
STATUS (TABLE) Abstract and page 1466. 1337100300022
ENDBIB 20 0 1337100300023
COMMON 2 3 1337100300024
ERR-1 ERR-2 1337100300025
PER-CENT PER-CENT 1337100300026
1.0 2.0 1337100300027
ENDCOMMON 3 0 1337100300028
DATA 2 1 1337100300029
DATA DATA-ERR 1337100300030
PC/FIS PC/FIS 1337100300031
6.62 0.15 1337100300032
ENDDATA 3 0 1337100300033
ENDSUBENT 32 0 1337100399999
ENDENTRY 3 0 1337199999999