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