ENTRY M0974 20190306 M100M097400000001
SUBENT M0974001 20190306 M100M097400100001
BIB 9 31 M097400100002
TITLE New photoneutron reaction cross section data for 153Eu M097400100003
and 165Ho. M097400100004
AUTHOR (V.V.Varlamov,A.I.Davydov) M097400100005
REFERENCE (C,2018VORNZH,,97,2018) M097400100006
INSTITUTE (4RUSMOS) M097400100007
INC-SOURCE (QMPH,ARAD) M097400100008
ANALYSIS The joint analysis of data for total (gamma,xn) and M097400100009
partial (gamma,n),(gamma,2n) and (gamma,3n) reactions M097400100010
obtained in various experiments was carried out. The M097400100011
new approach to analysis of systematic disagreements M097400100012
between data was proposed on the base of new M097400100013
criteria of systematic uncertainties presence - M097400100014
specially proposed transitional multiplicity M097400100015
functions M097400100016
Fi-theor = SIG(gamma,in)/SIG(gamma,xn). M097400100017
Using these functions calculated in the frame of M097400100018
combined photonuclear reaction model new reliable M097400100019
and free from problems of neutron multiplicity M097400100020
sorting data for photoneutron partial reactions M097400100021
cross sections M097400100022
SIG-eval(gamma,in) = Fi-theor x SIG-exp(gamma,xn) M097400100023
were evaluated using experimental neutron yield M097400100024
reaction cross sections SIG-exp(gamma,xn). M097400100025
ERR-ANALYS (DATA-ERR) Mean-root-squared errors. M097400100026
STATUS (TABLE) M097400100027
(APRVD) Approved by V.Varlamov. M097400100028
HISTORY (20180823C) Data were compiled at the Russia MSU SINP M097400100029
CDFE by V.Varlamov. M097400100030
(20190306A) Corrected by V.Varlamov: SUBENTS 010 - 017 M097400100031
deleted becaus of duplication with SUBENTS M0977005 - M097400100032
M0977008 and M0977012 - M0977015, correspondingly. M097400100033
ENDBIB 31 0 M097400100034
NOCOMMON 0 0 M097400100035
ENDSUBENT 34 0 M097400199999
SUBENT M0974002 20180823 M098M097400200001
BIB 3 9 M097400200002
REACTION (63-EU-153(G,X)0-NN-1,UNW,SIG,,,EVAL) M097400200003
ANALYSIS The total neutron reaction cross section obtained as M097400200004
sum: SIG(g,sn) = SIG(g,1n) + SIG(g,2n) + SIG(g,3n). M097400200005
STATUS (DEP,M0974003) M097400200006
Evaluated (g,1n) reaction cross section. M097400200007
(DEP,M0974004) M097400200008
Evaluated (g,2n) reaction cross section. M097400200009
(DEP,M0974005) M097400200010
Evaluated (g,3n) reaction cross section. M097400200011
ENDBIB 9 0 M097400200012
NOCOMMON 0 0 M097400200013
DATA 3 66 M097400200014
EN DATA DATA-ERR M097400200015
MEV MB MB M097400200016
8.8 2.66 1.99 M097400200017
9.1 25.07 8.35 M097400200018
9.4 38.71 11.51 M097400200019
9.7 52.33 12.34 M097400200020
10.0 47.60 10.60 M097400200021
10.3 68.69 13.58 M097400200022
10.7 88.07 16.87 M097400200023
11.0 115.50 21.50 M097400200024
11.3 145.30 26.42 M097400200025
11.6 176.70 29.97 M097400200026
11.9 197.50 33.29 M097400200027
12.2 228.00 38.18 M097400200028
12.5 238.80 39.78 M097400200029
12.8 239.20 39.83 M097400200030
13.1 223.50 37.31 M097400200031
13.4 222.10 37.02 M097400200032
13.7 224.90 37.42 M097400200033
14.1 214.60 36.12 M097400200034
14.4 232.00 40.27 M097400200035
14.7 245.50 44.90 M097400200036
15.0 241.40 40.83 M097400200037
15.3 245.10 41.51 M097400200038
15.6 249.40 42.65 M097400200039
15.9 224.40 39.83 M097400200040
16.2 221.90 42.38 M097400200041
16.5 204.00 40.50 M097400200042
16.8 204.80 41.79 M097400200043
17.1 181.50 37.76 M097400200044
17.5 173.90 36.75 M097400200045
17.8 168.00 35.97 M097400200046
18.1 145.50 31.67 M097400200047
18.4 129.40 28.53 M097400200048
18.7 122.90 27.57 M097400200049
19.0 112.60 25.74 M097400200050
19.3 106.50 24.70 M097400200051
19.6 91.52 21.59 M097400200052
19.9 86.84 20.77 M097400200053
20.2 83.20 20.14 M097400200054
20.6 80.73 19.74 M097400200055
20.9 78.27 19.38 M097400200056
21.2 75.17 18.77 M097400200057
21.5 63.30 16.59 M097400200058
21.8 57.31 15.08 M097400200059
22.1 50.83 13.90 M097400200060
22.4 58.81 15.62 M097400200061
22.7 56.21 13.97 M097400200062
23.0 55.05 16.11 M097400200063
23.3 51.82 16.48 M097400200064
23.6 40.01 13.48 M097400200065
24.0 48.52 15.20 M097400200066
24.3 51.00 16.32 M097400200067
24.6 38.41 14.65 M097400200068
24.9 27.67 11.85 M097400200069
25.2 40.36 16.21 M097400200070
25.5 45.13 18.93 M097400200071
25.8 33.86 13.99 M097400200072
26.1 24.33 14.26 M097400200073
26.4 29.05 13.42 M097400200074
26.8 23.14 14.03 M097400200075
27.1 22.50 11.93 M097400200076
27.4 28.78 16.66 M097400200077
27.7 26.09 13.62 M097400200078
28.0 23.46 14.97 M097400200079
28.3 33.14 16.17 M097400200080
28.6 36.15 19.02 M097400200081
28.9 40.94 20.77 M097400200082
ENDDATA 68 0 M097400200083
ENDSUBENT 82 0 M097400299999
SUBENT M0974003 20180823 M098M097400300001
BIB 4 22 M097400300002
REACTION ((63-EU-153(G,N)63-EU-152,,SIG,,,EVAL)+ M097400300003
(63-EU-153(G,N+P)62-SM-151,,SIG,,,EVAL)) M097400300004
ANALYSIS The contribution of partial reaction (g,n) cross M097400300005
section into the experimental total neutron yield M097400300006
reaction (g,xn) cross section obtained using M097400300007
quasimonoenergetic annihilation photons at Saclay M097400300008
was evaluated using specially theoretically M097400300009
calculated transitional multiplicity function - M097400300010
ratio M097400300011
F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M097400300012
by the way M097400300013
SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M097400300014
The neutron yield cross section was obtained at M097400300015
Livermore. M097400300016
REL-REF (R,L0016002,B.L.Berman+,J,PR,185,1576,1969) M097400300017
Experimental data for the total neutron yield M097400300018
reaction (g,xn) cross section. M097400300019
(E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097400300020
Theoretical preequilibrium model of photonuclear M097400300021
reactions based on the Fermi gas densities. M097400300022
STATUS (DEP,L0016002) M097400300023
The neutron yield reaction (g,xn) cross section. M097400300024
ENDBIB 22 0 M097400300025
NOCOMMON 0 0 M097400300026
DATA 3 66 M097400300027
EN DATA DATA-ERR M097400300028
MEV MB MB M097400300029
8.8 2.66 1.82 M097400300030
9.1 25.07 7.79 M097400300031
9.4 38.71 10.77 M097400300032
9.7 52.33 11.34 M097400300033
10.0 47.60 9.68 M097400300034
10.3 68.69 12.27 M097400300035
10.7 88.07 15.19 M097400300036
11.0 115.50 19.29 M097400300037
11.3 145.30 23.65 M097400300038
11.6 176.70 26.60 M097400300039
11.9 197.50 29.53 M097400300040
12.2 228.00 33.83 M097400300041
12.5 238.80 35.22 M097400300042
12.8 239.20 35.26 M097400300043
13.1 223.50 33.04 M097400300044
13.4 222.10 32.77 M097400300045
13.7 224.90 33.11 M097400300046
14.1 214.60 32.00 M097400300047
14.4 232.00 35.80 M097400300048
14.7 245.40 39.85 M097400300049
15.0 239.30 36.19 M097400300050
15.3 234.50 35.72 M097400300051
15.6 215.50 33.81 M097400300052
15.9 166.50 28.68 M097400300053
16.2 139.00 27.89 M097400300054
16.5 108.30 24.71 M097400300055
16.8 93.56 24.01 M097400300056
17.1 72.80 20.72 M097400300057
17.5 62.59 19.47 M097400300058
17.8 55.37 18.55 M097400300059
18.1 44.67 15.95 M097400300060
18.4 37.61 14.11 M097400300061
18.7 34.24 13.40 M097400300062
19.0 30.36 12.31 M097400300063
19.3 28.02 11.67 M097400300064
19.6 23.58 10.07 M097400300065
19.9 21.94 9.58 M097400300066
20.2 20.68 9.20 M097400300067
20.6 19.76 8.94 M097400300068
20.9 18.88 8.69 M097400300069
21.2 17.87 8.36 M097400300070
21.5 14.85 7.20 M097400300071
21.8 13.31 6.52 M097400300072
22.1 11.71 5.89 M097400300073
22.4 13.47 6.70 M097400300074
22.7 12.79 6.18 M097400300075
23.0 12.49 6.60 M097400300076
23.3 11.76 6.52 M097400300077
23.6 9.07 5.22 M097400300078
24.0 10.98 6.11 M097400300079
24.3 11.51 6.57 M097400300080
24.6 8.63 5.78 M097400300081
24.9 6.20 4.44 M097400300082
25.2 9.05 6.70 M097400300083
25.5 10.13 8.03 M097400300084
25.8 7.66 5.59 M097400300085
26.1 5.56 5.69 M097400300086
26.4 6.73 5.26 M097400300087
26.8 5.42 5.63 M097400300088
27.1 5.26 4.52 M097400300089
27.4 6.70 6.87 M097400300090
27.7 5.97 5.25 M097400300091
28.0 5.31 5.89 M097400300092
28.3 7.32 6.49 M097400300093
28.6 7.89 8.12 M097400300094
28.9 8.72 8.30 M097400300095
ENDDATA 68 0 M097400300096
ENDSUBENT 95 0 M097400399999
SUBENT M0974004 20180823 M098M097400400001
BIB 4 21 M097400400002
REACTION (63-EU-153(G,2N)63-EU-151,,SIG,,,EVAL) M097400400003
ANALYSIS The contribution of partial reaction (g,2n) cross M097400400004
section into the experimental total neutron yield M097400400005
reaction (g,xn) cross section obtained using M097400400006
quasimonoenergetic annihilation photons at Saclay M097400400007
was evaluated using specially theoretically M097400400008
calculated transitional multiplicity function - M097400400009
ratio M097400400010
F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M097400400011
by the way M097400400012
SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M097400400013
The neutron yield cross section was obtained at M097400400014
Livermore. M097400400015
REL-REF (R,L0016002,B.L.Berman+,J,PR,185,1576,1969) M097400400016
Experimental data for the total neutron yield M097400400017
reaction (g,xn) cross section. M097400400018
(E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097400400019
Theoretical preequilibrium model of photonuclear M097400400020
reactions based on the Fermi gas densities. M097400400021
STATUS (DEP,L0016002) M097400400022
The neutron yield reaction (g,xn) cross section. M097400400023
ENDBIB 21 0 M097400400024
NOCOMMON 0 0 M097400400025
DATA 3 48 M097400400026
EN DATA DATA-ERR M097400400027
MEV MB MB M097400400028
14.4 0.00 4.32 M097400400029
14.7 0.05 4.87 M097400400030
15.0 2.07 4.48 M097400400031
15.3 10.59 5.62 M097400400032
15.6 33.87 8.66 M097400400033
15.9 57.99 10.97 M097400400034
16.2 82.94 14.29 M097400400035
16.5 95.68 15.59 M097400400036
16.8 111.30 17.57 M097400400037
17.1 108.70 16.86 M097400400038
17.5 111.30 17.10 M097400400039
17.8 112.60 17.24 M097400400040
18.1 100.80 15.56 M097400400041
18.4 91.81 14.27 M097400400042
18.7 88.70 14.03 M097400400043
19.0 82.20 13.30 M097400400044
19.3 78.47 12.91 M097400400045
19.6 67.94 11.42 M097400400046
19.9 64.89 11.09 M097400400047
20.2 62.52 10.85 M097400400048
20.6 60.96 10.70 M097400400049
20.9 59.39 10.59 M097400400050
21.2 57.30 10.32 M097400400051
21.5 48.45 9.31 M097400400052
21.8 44.00 8.49 M097400400053
22.1 39.12 7.94 M097400400054
22.4 45.34 8.84 M097400400055
22.7 43.42 7.72 M097400400056
23.0 42.54 9.43 M097400400057
23.3 39.87 9.85 M097400400058
23.6 30.35 8.07 M097400400059
24.0 35.67 8.66 M097400400060
24.3 35.59 8.89 M097400400061
24.6 25.22 7.67 M097400400062
24.9 16.36 5.85 M097400400063
25.2 21.31 7.05 M097400400064
25.5 21.68 7.53 M097400400065
25.8 14.44 5.27 M097400400066
26.1 9.14 4.91 M097400400067
26.4 9.83 4.31 M097400400068
26.8 7.07 4.20 M097400400069
27.1 6.20 3.33 M097400400070
27.4 7.32 4.46 M097400400071
27.7 6.01 3.39 M097400400072
28.0 5.08 3.63 M097400400073
28.3 6.55 3.74 M097400400074
28.6 6.83 4.42 M097400400075
28.9 7.12 4.52 M097400400076
ENDDATA 50 0 M097400400077
ENDSUBENT 76 0 M097400499999
SUBENT M0974005 20180823 M098M097400500001
BIB 4 21 M097400500002
REACTION (63-EU-153(G,3N)63-EU-150,,SIG,,,EVAL) M097400500003
ANALYSIS The contribution of partial reaction (g,2n) cross M097400500004
section into the experimental total neutron yield M097400500005
reaction (g,xn) cross section obtained using M097400500006
quasimonoenergetic annihilation photons at Saclay M097400500007
was evaluated using specially theoretically M097400500008
calculated transitional multiplicity function - M097400500009
ratio M097400500010
F3-theor = SIG-theor(g,3n)/SIG-theor(g,xn) M097400500011
by the way M097400500012
SIG-eval(g,3n) = (F3-theor)x(SIG-exp(g,xn)). M097400500013
The neutron yield cross section was obtained at M097400500014
Livermore. M097400500015
REL-REF (R,L0016002,B.L.Berman+,J,PR,185,1576,1969) M097400500016
Experimental data for the total neutron yield M097400500017
reaction (g,xn) cross section. M097400500018
(E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097400500019
Theoretical preequilibrium model of photonuclear M097400500020
reactions based on the Fermi gas densities. M097400500021
STATUS (DEP,L0016002) M097400500022
The neutron yield reaction (g,xn) cross section. M097400500023
ENDBIB 21 0 M097400500024
NOCOMMON 0 0 M097400500025
DATA 3 21 M097400500026
EN DATA DATA-ERR M097400500027
MEV MB MB M097400500028
22.7 0.00 0.06 M097400500029
23.0 0.02 0.06 M097400500030
23.3 0.18 0.09 M097400500031
23.6 0.59 0.17 M097400500032
24.0 1.87 0.42 M097400500033
24.3 3.90 0.85 M097400500034
24.6 4.54 1.19 M097400500035
24.9 5.09 1.55 M097400500036
25.2 10.00 2.44 M097400500037
25.5 13.32 3.35 M097400500038
25.8 11.75 3.12 M097400500039
26.1 9.62 3.65 M097400500040
26.4 12.48 3.84 M097400500041
26.8 10.65 4.18 M097400500042
27.1 11.04 4.07 M097400500043
27.4 14.75 5.32 M097400500044
27.7 14.10 4.97 M097400500045
28.0 13.06 5.43 M097400500046
28.3 19.26 5.93 M097400500047
28.6 21.43 6.46 M097400500048
28.9 25.10 7.94 M097400500049
ENDDATA 23 0 M097400500050
ENDSUBENT 49 0 M097400599999
SUBENT M0974006 20180823 M098M097400600001
BIB 3 3 M097400600002
REACTION (63-EU-153(G,X)0-NN-1,UNW,INT,,,EVAL) M097400600003
ANALYSIS Integration of evaluated cross section. M097400600004
STATUS (DEP,M0974002) Evaluated cross section. M097400600005
ENDBIB 3 0 M097400600006
NOCOMMON 0 0 M097400600007
DATA 3 3 M097400600008
EN-MAX DATA DATA-ERR M097400600009
MEV MB*MEV MB*MEV M097400600010
14.9 955.1 48.2 M097400600011
22.3 1990.3 72.2 M097400600012
29.0 2245.6 76.7 M097400600013
ENDDATA 5 0 M097400600014
ENDSUBENT 13 0 M097400699999
SUBENT M0974007 20180823 M098M097400700001
BIB 3 4 M097400700002
REACTION ((63-EU-153(G,N)63-EU-152,,INT,,,EVAL)+ M097400700003
(63-EU-153(G,N+P)62-SM-151,,INT,,,EVAL)) M097400700004
ANALYSIS Integration of evaluated cross section. M097400700005
STATUS (DEP,M0974003) Evaluated cross section. M097400700006
ENDBIB 4 0 M097400700007
NOCOMMON 0 0 M097400700008
DATA 3 3 M097400700009
EN-MAX DATA DATA-ERR M097400700010
MEV MB*MEV MB*MEV M097400700011
14.9 954.7 42.8 M097400700012
22.3 1471.7 54.5 M097400700013
29.0 1529.3 55.5 M097400700014
ENDDATA 5 0 M097400700015
ENDSUBENT 14 0 M097400799999
SUBENT M0974008 20180823 M098M097400800001
BIB 3 3 M097400800002
REACTION (63-EU-153(G,2N)63-EU-151,,INT,,,EVAL) M097400800003
ANALYSIS Integration of evaluated cross section. M097400800004
STATUS (DEP,M0974004) Evaluated cross section. M097400800005
ENDBIB 3 0 M097400800006
NOCOMMON 0 0 M097400800007
DATA 3 2 M097400800008
EN-MAX DATA DATA-ERR M097400800009
MEV MB*MEV MB*MEV M097400800010
22.3 518.6 22.6 M097400800011
29.0 655.1 25.1 M097400800012
ENDDATA 4 0 M097400800013
ENDSUBENT 12 0 M097400899999
SUBENT M0974009 20180823 M098M097400900001
BIB 3 3 M097400900002
REACTION (63-EU-153(G,3N)63-EU-150,,INT,,,EVAL) M097400900003
ANALYSIS Integration of evaluated cross section. M097400900004
STATUS (DEP,M0974004) Evaluated cross section. M097400900005
ENDBIB 3 0 M097400900006
NOCOMMON 0 0 M097400900007
DATA 3 1 M097400900008
EN-MAX DATA DATA-ERR M097400900009
MEV MB*MEV MB*MEV M097400900010
29.0 68.1 3.6 M097400900011
ENDDATA 3 0 M097400900012
ENDSUBENT 11 0 M097400999999
NOSUBENT M0974010 20181010 M100M097401000001
NOSUBENT M0974011 20181010 M100M097401100001
NOSUBENT M0974012 20181010 M100M097401200001
NOSUBENT M0974013 20181010 M100M097401300001
NOSUBENT M0974014 20181010 M100M097401400001
NOSUBENT M0974015 20181010 M100M097401500001
NOSUBENT M0974016 20181010 M100M097401600001
NOSUBENT M0974017 20181010 M100M097401700001
ENDENTRY 17 0 M097499999999