SUBENT 21816001 20101118 22252181600100001
BIB 14 60 2181600100002
INSTITUTE (2FR CAD) experimental site. 2181600100003
(2ZZZITU) authors. 2181600100004
REFERENCE (C,82ANTWER,,175,198209) 2181600100005
AUTHOR (A.Cricchio,R.Ernstberger,L.Koch,R.Wellum) 2181600100006
TITLE -the TACO experiment for the determination of 2181600100007
integral cross sections in a fast reactor.- 2181600100008
FACILITY (REAC,2FR CAD) RAPSODIE FORTISSIMA reactor. 2181600100009
INC-SOURCE (REAC ) reactor neutrons. 2181600100010
INC-SPECT .Neutrons from fast reactor RAPSODIE. The 2181600100011
spectrum is given in table 2 of the 82ANTWER,175,1982 2181600100012
energy-range (keV) neutrons (%) 2181600100013
--------------------------------------------- 2181600100014
0.748 - 1.23 0.03 2181600100015
1.23 - 2.04 0.115 2181600100016
2.04 - 3.36 0.165 2181600100017
3.36 - 5.53 0.207 2181600100018
5.53 - 9.12 0.418 2181600100019
9.12 - 15.0 0.809 2181600100020
15.0 - 24.8 2.00 2181600100021
24.8 - 40.9 3.03 2181600100022
40.9 - 67.4 4.44 2181600100023
67.4 - 111. 7.14 2181600100024
111. - 183. 9.89 2181600100025
183. - 302. 14.2 2181600100026
302. - 498. 13.5 2181600100027
498. - 821. 17.4 2181600100028
821. - 1350. 10.6 2181600100029
1350. - 2230. 8.69 2181600100030
2230. - 3680. 5.18 2181600100031
3680. - 14500. 2.17 2181600100032
--------------------------------------------- 2181600100033
SAMPLE .Each nuclide to be irradiated was dissolved 2181600100034
in nitric acid. Aliquots of the solutions were 2181600100035
placed in thin-walled aluminium capsules and 2181600100036
dried under vacuum. The nitrates were then 2181600100037
decomposed by heating. The capsules were closed 2181600100038
under vacuum and collapsed when atmospheric 2181600100039
pressure was restored. The capsules were 2181600100040
folded and placed in stainless steel cans of 2181600100041
4.3 mm outer diameter and 30 mm length which 2181600100042
were in turn sealed by electron beam welding. 2181600100043
METHOD (CHSEP,MASSP) the concentration of the isotopes 2181600100044
before and after a long irradiation were 2181600100045
determined by using a mass spectrometer. 2181600100046
therefore a non irradiated sample was kept 2181600100047
for comparison. 2181600100048
ADD-RES (COMP) .Compared with values derived from point-wise 2181600100049
data from KEDAK. 2181600100050
STATUS (TABLE).Data taken from tables in 82ANTWER,175,1982. 2181600100051
CORRECTION .Interferences due to natural background from the 2181600100052
filament. Corrections were applied based on 2181600100053
selected masses, naturally abundant but depleted 2181600100054
in the irradiated material. 2181600100055
ERR-ANALYS .no details given. Most measurements were 2181600100056
done twice to estimate the measurement errors. 2181600100057
HISTORY (19830126C) G.C. 2181600100058
(19830210E) 2181600100059
(20101118A) SD:Updated to new date formats,lower case. 2181600100060
corrected according to last EXFOR rules and Dict. 2181600100061
EN-DUMMY corrected: 1.5 MeV => 0.659 MeV 2181600100062
ENDBIB 60 0 2181600100063
COMMON 1 3 2181600100064
EN-DUMMY 2181600100065
MEV 2181600100066
0.650 2181600100067
ENDCOMMON 3 0 2181600100068
ENDSUBENT 67 0 2181600199999
SUBENT 21816018 20101118 22252181601800001
BIB 2 2 2181601800002
REACTION (46-PD-106(N,G)46-PD-107,,SIG,,FST) 2181601800003
STATUS (TABLE) .Data taken from table 5 of 82ANTWER,175,1982.2181601800004
ENDBIB 2 0 2181601800005
NOCOMMON 0 0 2181601800006
DATA 1 1 2181601800007
DATA 2181601800008
B 2181601800009
9.4000E-02 2181601800010
ENDDATA 3 0 2181601800011
ENDSUBENT 10 0 2181601899999