ENTRY 40062 20220127 42044006200000001
SUBENT 40062001 20220127 42044006200100001
BIB 8 24 4006200100002
TITLE Cross sections and resonance integrals for capture and 4006200100003
fission in long-lived americium isotopes 4006200100004
AUTHOR (M.A.Bak, A.S.Krivokhatskii, K.A.Petrzhak, Yu.G.Petrov,4006200100005
Yu.F.Romanov, E.A.Shlyamin) 4006200100006
REFERENCE (J,AE,23,316,196710) Issue 4. 4006200100007
(J,SJA,23,1059,1967) Engl.transl.of J,AE,23,316,1967 4006200100008
#doi:10.1007/BF01120465 4006200100009
(R,YFI-5,49,1967) 4006200100010
(R,INDC(CCP)-1,51,1967) 4006200100011
INSTITUTE (4RUSRI) 4006200100012
FACILITY (REAC,4RUSRI) Thermal reactor WWR-M 4006200100013
COMMENT Exact meaning of cadmium neutron spectrum limit was not4006200100014
indicated. Cadmium neutron spectrum limit was supposed 4006200100015
to be equal to 0.4 eV 4006200100016
STATUS (TABLE) Table 2 of At.Energy,v.23,is.4,p.316,1967 . 4006200100017
= Table 1 of INDC(CCP)-1,p.51,1967 4006200100018
HISTORY (19710405C) 4006200100019
(20051101A) (M.M.) Correction of Reaction codes, 4006200100020
Subents 9-11 were added 4006200100021
(20130716A) Subent 003 was corrected. 4006200100022
Some misprints were corrected. 4006200100023
BIB information was updated. 4006200100024
(20220127A) Ref. INDC(CCP) was added. 4006200100025
Update for current rules and dictionaries. 4006200100026
ENDBIB 24 0 4006200100027
NOCOMMON 0 0 4006200100028
ENDSUBENT 27 0 4006200199999
SUBENT 40062002 20220127 42044006200200001
BIB 11 20 4006200200002
REACTION (95-AM-241(N,G)95-AM-242-G,,SIG) 4006200200003
INC-SOURCE (REAC) Samples were irradiated in neutron flux from 4006200200004
1.5E+13 to 1.0E+14 neutron/cm**2/sec. 4006200200005
SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 4006200200006
0.1 % of Pu-239) on backing of beryllium or titanium 4006200200007
DECAY-DATA (95-AM-242-G,16.HR) 4006200200008
METHOD (ACTIV) For determination of thermal cross sections 4006200200009
samples were irradiated with cadmium cover and without 4006200200010
one. 4006200200011
Irradiation time was within 5-100 hours 4006200200012
DETECTOR (SI) 4006200200013
MONITOR (79-AU-197(N,G)79-AU-198,,SIG) 4006200200014
(93-NP-237(N,A)91-PA-234,,SIG) 4006200200015
They were used for measuring of neutron flux 4006200200016
RAD-DET (96-CM-242,A) 4006200200017
COMMENT In COMMON section EN-MIN and EN-MAX of incident 4006200200018
spectrum were given 4006200200019
ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 4006200200020
articles. 4006200200021
HISTORY (20220127A) PART-DET -> RAD-DET 4006200200022
ENDBIB 20 0 4006200200023
COMMON 2 3 4006200200024
EN-MIN EN-MAX 4006200200025
EV EV 4006200200026
0.0 4.0000E-01 4006200200027
ENDCOMMON 3 0 4006200200028
DATA 2 1 4006200200029
DATA DATA-ERR 4006200200030
B B 4006200200031
670. 60. 4006200200032
ENDDATA 3 0 4006200200033
ENDSUBENT 32 0 4006200299999
SUBENT 40062003 20220127 42044006200300001
BIB 12 33 4006200300002
REACTION (95-AM-241(N,G)95-AM-242-M,,SIG) 4006200300003
INC-SOURCE (REAC) Samples were irradiated in neutron flux from 4006200300004
1.5E+13 to 1.0E+14 neutron/cm**2/sec. Irradiation 4006200300005
time was within 5-100 hours. For determination 4006200300006
of Am-242-M quantity - 5.0E+7 neutron/cm**2/sec 4006200300007
neutron flux was used 4006200300008
SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 4006200300009
0.1 % of Pu-239) on backing of beryllium or titanium 4006200300010
METHOD (ACTIV) For determination of thermal cross sections 4006200300011
samples were irradiated with cadmium cover and without 4006200300012
one 4006200300013
DETECTOR (FISCH) For determination of Am-242-M quantity 4006200300014
double fission chamber was used. 4006200300015
(SI) For samples alpha-activity measuring 4006200300016
MONITOR ((MONIT1)95-AM-242-M1(N,F),,SIG) 4006200300017
(79-AU-197(N,G)79-AU-198,,SIG) 4006200300018
For measuring of neutron flux gold 4006200300019
was used 4006200300020
(93-NP-237(N,A)91-PA-234,,SIG) 4006200300021
For measuring of neutron flux neptunium 4006200300022
was used 4006200300023
MONIT-REF ((MONIT1)12563002,K.Wolfsberg+,J,JNE/AB,20,588,1966) 4006200300024
ANALYSIS Am-241 capture c-s was measured by accumulated Am-242m 4006200300025
number defined by Am-242m thermal fission c-s . 4006200300026
PART-DET (FF) 4006200300027
(A) 4006200300028
COMMENT In COMMON section EN-MIN, EN-MAX of incident spectrum 4006200300029
and last fission cross section data of americium 242 4006200300030
in metastable state are given 4006200300031
ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 4006200300032
articles. 4006200300033
HISTORY (20130716A) AM-242-M1 -> AM-242-M was corrected in 4006200300034
Reaction according to the comment of N.Otsuka(NDS,IAEA)4006200300035
ENDBIB 33 0 4006200300036
COMMON 5 3 4006200300037
EN-MIN EN-MAX MONIT1 MONIT1-ERR EN-NRM 4006200300038
EV EV B B EV 4006200300039
0.0 4.0000E-01 7200. 300. 0.0253 4006200300040
ENDCOMMON 3 0 4006200300041
DATA 2 1 4006200300042
DATA DATA-ERR 4006200300043
B B 4006200300044
70. 5. 4006200300045
ENDDATA 3 0 4006200300046
ENDSUBENT 45 0 4006200399999
SUBENT 40062004 20220127 42044006200400001
BIB 8 17 4006200400002
REACTION (95-AM-242(N,F),,SIG) 4006200400003
INC-SOURCE (REAC) The samples were irradiated in 5.0E+7 neutron / 4006200400004
cm**2/sec neutron flux 4006200400005
SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 4006200400006
0.1 % of Pu-239) on backing of beryllium or titanium 4006200400007
METHOD Counter ratio.For determination of thermal cross4006200400008
sections samples were irradiated with cadmium cover and4006200400009
without one 4006200400010
DETECTOR (FISCH) In experiments double ionization chamber 4006200400011
was used 4006200400012
(SI) For alpha-activity measuring 4006200400013
PART-DET (FF) 4006200400014
(A) 4006200400015
COMMENT In COMMON section EN-MIN and EN-MAX of incident 4006200400016
spectrum were given 4006200400017
ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 4006200400018
articles. 4006200400019
ENDBIB 17 0 4006200400020
COMMON 2 3 4006200400021
EN-MIN EN-MAX 4006200400022
EV EV 4006200400023
0.0 4.0000E-01 4006200400024
ENDCOMMON 3 0 4006200400025
DATA 2 1 4006200400026
DATA DATA-ERR 4006200400027
B B 4006200400028
2100. 200. 4006200400029
ENDDATA 3 0 4006200400030
ENDSUBENT 29 0 4006200499999
SUBENT 40062005 20220127 42044006200500001
BIB 10 20 4006200500002
REACTION (95-AM-243(N,G)95-AM-244,,SIG) 4006200500003
INC-SOURCE (REAC) Samples were irradiated in neutron flux from 4006200500004
1.5E+13 to 1.0E+14 neutrons/cm**2/sec. Irradiation 4006200500005
time was within 5-100 hours 4006200500006
SAMPLE A few micrograms of Am-241 and Am-243 mixture 4006200500007
(7.5 % of Am-241 and 91.5 %t of Am-243) 4006200500008
on backing of beryllium or titanium 4006200500009
METHOD (ACTIV) For determination of thermal cross sections 4006200500010
samples were irradiated with cadmium cover and without 4006200500011
one 4006200500012
DETECTOR Alpha spectrometer with silicon detector 4006200500013
MONITOR (79-AU-197(N,G)79-AU-198,,SIG) 4006200500014
(93-NP-237(N,A)91-PA-234,,SIG) 4006200500015
They are used for measuring neutron flux 4006200500016
RAD-DET (96-CM-244,A) 4006200500017
COMMENT In COMMON section EN-MIN and EN-MAX of incident 4006200500018
spectrum were given 4006200500019
ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 4006200500020
articles. 4006200500021
HISTORY (20220127A) PART-DET -> RAD-DET 4006200500022
ENDBIB 20 0 4006200500023
COMMON 2 3 4006200500024
EN-MIN EN-MAX 4006200500025
EV EV 4006200500026
0.0 4.0000E-01 4006200500027
ENDCOMMON 3 0 4006200500028
DATA 2 1 4006200500029
DATA DATA-ERR 4006200500030
B B 4006200500031
73. 6. 4006200500032
ENDDATA 3 0 4006200500033
ENDSUBENT 32 0 4006200599999
SUBENT 40062006 20220127 42044006200600001
BIB 7 15 4006200600002
REACTION (95-AM-241(N,G)95-AM-242-G,,RI) 4006200600003
INC-SOURCE (REAC) Samples were irradiated in neutron flux from 4006200600004
1.5E+13 to 1.0E+14 neutrons/cm**2/sec. 4006200600005
SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 4006200600006
0.1 % of Pu-239) on backing of beryllium or titanium 4006200600007
METHOD Counter ratio. For relative measurement of 4006200600008
resonance integrals method of cadmium ratios was used 4006200600009
MONITOR ((MONIT1)79-AU-197(N,G)79-AU-198,,RI) 4006200600010
((MONIT2)79-AU-197(N,G)79-AU-198,,SIG) 4006200600011
COMMENT In Common Section EN-MIN of incident spectrum,capture 4006200600012
resonance integral and capture cross section of Au-197 4006200600013
were given. EN-MAX of incident spectrum was equal to 4006200600014
infinity 4006200600015
ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 4006200600016
articles. 4006200600017
ENDBIB 15 0 4006200600018
COMMON 5 3 4006200600019
EN-MIN MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 4006200600020
EV B B B B 4006200600021
4.0000E-01 1.5580E+03 5.0000E+01 9.8800E+01 3.0000E-01 4006200600022
ENDCOMMON 3 0 4006200600023
DATA 2 1 4006200600024
DATA DATA-ERR 4006200600025
B B 4006200600026
2100. 200. 4006200600027
ENDDATA 3 0 4006200600028
ENDSUBENT 27 0 4006200699999
SUBENT 40062007 20220127 42044006200700001
BIB 8 16 4006200700002
REACTION (95-AM-241(N,G)95-AM-242-M,,RI) 4006200700003
INC-SOURCE (REAC) 4006200700004
SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 4006200700005
0.1 % of Pu-239) on backing of beryllium or titanium 4006200700006
METHOD Counter ratio. For relative measurement of 4006200700007
resonance integrals, method of cadmium ratios was used 4006200700008
MONITOR ((MONIT1)79-AU-197(N,G)79-AU-198,,RI) 4006200700009
((MONIT2)79-AU-197(N,G)79-AU-198,,SIG) 4006200700010
ANALYSIS Resonance integral was determined using formula (25) 4006200700011
of Sov.J.At.Energy,v.23,p.1059,1967 4006200700012
COMMENT In Common Section EN-MIN of incident spectrum,capture 4006200700013
resonance integral and capture cross section of Au-197 4006200700014
were given. EN-MAX of incident spectrum was equal to 4006200700015
infinity 4006200700016
ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 4006200700017
articles. 4006200700018
ENDBIB 16 0 4006200700019
COMMON 5 3 4006200700020
EN-MIN MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 4006200700021
EV B B B B 4006200700022
4.0000E-01 1558. 50. 98.8 0.3 4006200700023
ENDCOMMON 3 0 4006200700024
DATA 2 1 4006200700025
DATA DATA-ERR 4006200700026
B B 4006200700027
300. 30. 4006200700028
ENDDATA 3 0 4006200700029
ENDSUBENT 28 0 4006200799999
SUBENT 40062008 20220127 42044006200800001
BIB 8 18 4006200800002
REACTION (95-AM-243(N,G)95-AM-244,,RI) 4006200800003
INC-SOURCE (REAC) Samples were irradiated in neutron flux from 4006200800004
1.5E+13 to 1.0E+14 neutrons/cm**2/sec. 4006200800005
SAMPLE A few micrograms of Am-241 and Am-243 mixture 4006200800006
(7.5 % of Am-241 and 91.5 % of Am-243) 4006200800007
on backing of beryllium or titanium 4006200800008
METHOD Counter ratio. For relative measurement of 4006200800009
resonance integrals method of cadmium ratios was used 4006200800010
MONITOR ((MONIT1)79-AU-197(N,G)79-AU-198,,RI) 4006200800011
((MONIT2)79-AU-197(N,G)79-AU-198,,SIG) 4006200800012
ANALYSIS Resonance integral was determined using formula (25) 4006200800013
of Sov.J.At.Energy,v.23,p.1059,1967 4006200800014
COMMENT In common section EN-MIN incident spectrum and capture 4006200800015
resonance integral and capture cross section of Au-197 4006200800016
are given. EN-MAX incident spectrum was equal to 4006200800017
infinity 4006200800018
ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 4006200800019
articles. 4006200800020
ENDBIB 18 0 4006200800021
COMMON 5 3 4006200800022
EN-MIN MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 4006200800023
EV B B B B 4006200800024
4.0000E-01 1558. 50. 98.8 0.3 4006200800025
ENDCOMMON 3 0 4006200800026
DATA 2 1 4006200800027
DATA DATA-ERR 4006200800028
B B 4006200800029
2300. 200. 4006200800030
ENDDATA 3 0 4006200800031
ENDSUBENT 30 0 4006200899999
SUBENT 40062009 20220127 42044006200900001
BIB 8 17 4006200900002
REACTION (95-AM-241(N,F),,SIG) 4006200900003
INC-SOURCE (REAC) The samples were irradiated by flux from 4006200900004
1.5E+13 to 1.0E+14 neutron/cm**2/sec. Irradiation 4006200900005
time was within 5-100 hours 4006200900006
SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 4006200900007
0.1 % of Pu-239) on backing of beryllium or titanium 4006200900008
METHOD Counter ratio.For determination of thermal cross4006200900009
sections samples were irradiated with cadmium cover and4006200900010
without one 4006200900011
DETECTOR (FISCH) In experiments double ionization chamber 4006200900012
was used 4006200900013
PART-DET (FF) 4006200900014
(A) 4006200900015
COMMENT In common section EN-MIN and EN-MAX Of incident 4006200900016
spectrum were given 4006200900017
ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 4006200900018
articles. 4006200900019
ENDBIB 17 0 4006200900020
COMMON 2 3 4006200900021
EN-MIN EN-MAX 4006200900022
EV EV 4006200900023
0.0 4.0000E-01 4006200900024
ENDCOMMON 3 0 4006200900025
DATA 2 1 4006200900026
DATA DATA-ERR 4006200900027
B B 4006200900028
3.15 0.10 4006200900029
ENDDATA 3 0 4006200900030
ENDSUBENT 29 0 4006200999999
SUBENT 40062010 20220127 42044006201000001
BIB 9 19 4006201000002
REACTION (95-AM-241(N,F),,RI) 4006201000003
INC-SOURCE (REAC) The samples were irradiated by flux from 4006201000004
1.5E+13 to 1.0E+14 neutron/cm**2/sec. Irradiation 4006201000005
time was within 5-100 hours 4006201000006
SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 4006201000007
0.1 % of Pu-239) on backing of beryllium or titanium 4006201000008
METHOD Counter ratio.For determination of thermal cross4006201000009
sections samples were irradiated with cadmium cover and4006201000010
without one 4006201000011
DETECTOR (FISCH) In experiments double ionization chamber 4006201000012
was used 4006201000013
PART-DET (FF) 4006201000014
(A) 4006201000015
MONITOR ((MONIT1)79-AU-197(N,G)79-AU-198,,RI) 4006201000016
((MONIT2)79-AU-197(N,G)79-AU-198,,SIG) 4006201000017
ANALYSIS Resonance integral was determined using formula (25) 4006201000018
of Sov.J.At.Energy,v.23,p.1059,1967 4006201000019
ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 4006201000020
article 4006201000021
ENDBIB 19 0 4006201000022
COMMON 5 3 4006201000023
EN-MIN MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 4006201000024
EV B B B B 4006201000025
4.0000E-01 1558. 50. 98.8 0.3 4006201000026
ENDCOMMON 3 0 4006201000027
DATA 2 1 4006201000028
DATA DATA-ERR 4006201000029
B B 4006201000030
21. 2. 4006201000031
ENDDATA 3 0 4006201000032
ENDSUBENT 31 0 4006201099999
SUBENT 40062011 20220127 42044006201100001
BIB 8 17 4006201100002
REACTION (95-AM-242(N,F),,RI) 4006201100003
INC-SOURCE (REAC) The samples were irradiated by flux 5.E+07 4006201100004
neutron/cm**2/sec. 4006201100005
SAMPLE A few micrograms of Am-241 (99.9 % of Am-241 and 4006201100006
0.1 % of Pu-239) on backing of beryllium or titanium 4006201100007
METHOD Counter ratio.For determination of thermal cross4006201100008
sections samples were irradiated with cadmium cover and4006201100009
without one 4006201100010
DETECTOR (FISCH) In experiments double ionization chamber 4006201100011
was used 4006201100012
(SI) For alpha-activity measuring 4006201100013
PART-DET (FF) 4006201100014
(A) 4006201100015
MONITOR ((MONIT1)79-AU-197(N,G)79-AU-198,,RI) 4006201100016
((MONIT2)79-AU-197(N,G)79-AU-198,,SIG) 4006201100017
ANALYSIS Resonance integral was determined using formula (25) 4006201100018
of Sov.J.At.Energy,v.23,p.1059,1967 4006201100019
ENDBIB 17 0 4006201100020
COMMON 5 3 4006201100021
EN-MIN MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 4006201100022
EV B B B B 4006201100023
4.0000E-01 1558. 50. 98.8 0.3 4006201100024
ENDCOMMON 3 0 4006201100025
DATA 1 1 4006201100026
DATA-MAX 4006201100027
B 4006201100028
300. 4006201100029
ENDDATA 3 0 4006201100030
ENDSUBENT 29 0 4006201199999
ENDENTRY 11 0 4006299999999