ENTRY M0975 20190121 M099M097500000001
SUBENT M0975001 20190121 M099M097500100001
BIB 9 26 M097500100002
TITLE New reliable data on the photodisintegration of 160Gd M097500100003
AUTHOR (V.V.Varlamov,V.D.Kaidarova,V.N.Orlin) M097500100004
REFERENCE (J,MPM,1,1910202,2019) M097500100005
INSTITUTE (4RUSMOS) M097500100006
INC-SOURCE (QMPH,ARAD) M097500100007
ANALYSIS The joint analysis of data for total (g,xn) and M097500100008
partial (g,n), (g,2n) and (g,3n) reactions obtained M097500100009
in various experiments was carried out. The new M097500100010
approach to analysis of systematic disagreements M097500100011
between data was proposed on the base of new M097500100012
criteria of systematic uncertainties presence - M097500100013
specially proposed transitional multiplicity M097500100014
functions M097500100015
Fi-theor = SIG(g,in)/SIG(g,xn). M097500100016
Using these functions calculated in the frame of M097500100017
combined photonuclear reaction model new reliable M097500100018
and free from problems of neutron multiplicity M097500100019
sorting data for photoneutron partial reactions M097500100020
cross sections M097500100021
SIG-eval(g,in) = Fi-theor x SIG-exp(g,xn) M097500100022
were evaluated using experimental neutron yield M097500100023
reaction cross sections SIG-exp(g,xn). M097500100024
ERR-ANALYS (DATA-ERR) Root-mean-squared errors. M097500100025
STATUS (APRVD) By V.Varlamov. M097500100026
HISTORY (20190121C) Data were compiled at the Russia MSU SINP M097500100027
CDFE by V.Varlamov. M097500100028
ENDBIB 26 0 M097500100029
NOCOMMON 0 0 M097500100030
ENDSUBENT 29 0 M097500199999
SUBENT M0975002 20190121 M099M097500200001
BIB 3 10 M097500200002
REACTION (64-GD-160(G,X)0-NN-1,UNW,SIG,,,EVAL) M097500200003
ANALYSIS The total neutron reaction cross section obtained as M097500200004
sum: SIG(g,sn) = SIG(g,n) + SIG(g,2n) + SIG(g,3n). M097500200005
STATUS (TABLE) Data plotted in Fig. 3. M097500200006
(DEP,M0975003) M097500200007
Evaluated (g,n) reaction cross section. M097500200008
(DEP,M0975004) M097500200009
Evaluated (g,2n) reaction cross section. M097500200010
(DEP,M0975005) M097500200011
Evaluated (g,3n) reaction cross section. M097500200012
ENDBIB 10 0 M097500200013
NOCOMMON 0 0 M097500200014
DATA 3 50 M097500200015
EN DATA DATA-ERR M097500200016
MEV MB MB M097500200017
7.91 20.53 6.74 M097500200018
8.31 32.02 6.15 M097500200019
8.71 36.68 6.65 M097500200020
9.11 43.00 6.84 M097500200021
9.51 52.04 6.73 M097500200022
9.91 65.07 7.77 M097500200023
10.31 92.73 10.59 M097500200024
10.71 120.17 12.77 M097500200025
11.11 142.11 16.36 M097500200026
11.51 214.29 23.54 M097500200027
11.91 264.36 28.53 M097500200028
12.31 278.09 30.00 M097500200029
12.71 269.85 29.42 M097500200030
13.11 256.39 28.21 M097500200031
13.51 250.88 27.81 M097500200032
13.91 222.18 23.01 M097500200033
14.31 245.18 20.48 M097500200034
14.71 236.39 17.55 M097500200035
15.11 260.72 19.46 M097500200036
15.51 249.41 18.85 M097500200037
15.91 270.64 19.88 M097500200038
16.31 264.47 19.96 M097500200039
16.71 248.83 19.90 M097500200040
17.11 223.65 17.65 M097500200041
17.51 207.80 16.74 M097500200042
17.91 177.00 14.48 M097500200043
18.31 156.13 13.21 M097500200044
18.71 135.79 11.70 M097500200045
19.11 125.32 11.14 M097500200046
19.51 106.24 9.82 M097500200047
20.11 99.11 9.40 M097500200048
20.31 86.78 8.00 M097500200049
20.71 70.19 6.93 M097500200050
21.11 60.28 6.36 M097500200051
21.51 58.17 7.59 M097500200052
21.91 48.76 7.21 M097500200053
22.31 49.84 7.29 M097500200054
22.71 51.72 5.80 M097500200055
23.11 51.77 6.11 M097500200056
23.51 49.70 6.23 M097500200057
23.91 47.56 5.87 M097500200058
24.31 47.11 5.57 M097500200059
24.71 46.99 5.46 M097500200060
25.31 31.32 4.77 M097500200061
25.91 32.91 5.21 M097500200062
26.51 39.51 5.53 M097500200063
27.11 22.00 4.06 M097500200064
27.71 20.56 4.56 M097500200065
28.31 31.25 5.13 M097500200066
29.51 26.72 8.95 M097500200067
ENDDATA 52 0 M097500200068
ENDSUBENT 67 0 M097500299999
SUBENT M0975003 20190121 M099M097500300001
BIB 4 21 M097500300002
REACTION ((64-GD-160(G,N)64-GD-159,,SIG,,,EVAL)+ M097500300003
(64-GD-160(G,N+P)63-EU-158,,SIG,,,EVAL)) M097500300004
ANALYSIS The contribution of partial reaction (g,n) cross M097500300005
section into the experimental total neutron yield M097500300006
reaction (g,xn) cross section obtained using M097500300007
quasimonoenergetic annihilation photons at Livermore M097500300008
(USA) was evaluated using specially theoretically M097500300009
calculated transitional multiplicity function - M097500300010
ratio M097500300011
F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M097500300012
by the way M097500300013
SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M097500300014
REL-REF (R,L0016006,B.L.Berman+,J,PR,185,1576,1969) M097500300015
Experimental data for the total neutron yield M097500300016
reaction (g,xn) cross section. M097500300017
(E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097500300018
Theoretical preequilibrium model of photonuclear M097500300019
reactions based on the Fermi gas densities. M097500300020
STATUS (TABLE) Data plotted in Fig. 3. M097500300021
(DEP,L0016006) M097500300022
The neutron yield reaction (g,xn) cross section. M097500300023
ENDBIB 21 0 M097500300024
NOCOMMON 0 0 M097500300025
DATA 3 50 M097500300026
EN DATA DATA-ERR M097500300027
MEV MB MB M097500300028
7.91 20.53 6.74 M097500300029
8.31 32.02 6.15 M097500300030
8.71 36.68 6.65 M097500300031
9.11 43.00 6.84 M097500300032
9.51 52.04 6.73 M097500300033
9.91 65.07 7.77 M097500300034
10.31 92.73 10.59 M097500300035
10.71 120.17 12.77 M097500300036
11.11 142.11 16.36 M097500300037
11.51 214.29 23.54 M097500300038
11.91 264.36 28.53 M097500300039
12.31 278.09 30.00 M097500300040
12.71 269.85 29.42 M097500300041
13.11 256.39 28.21 M097500300042
13.51 250.88 27.81 M097500300043
13.91 214.10 22.99 M097500300044
14.31 189.26 19.64 M097500300045
14.71 139.51 14.42 M097500300046
15.11 126.32 13.33 M097500300047
15.51 107.55 11.39 M097500300048
15.91 107.25 10.91 M097500300049
16.31 97.09 10.01 M097500300050
16.71 83.95 9.03 M097500300051
17.11 69.86 7.30 M097500300052
17.51 60.26 6.33 M097500300053
17.91 50.87 5.41 M097500300054
18.31 40.03 4.30 M097500300055
18.71 33.38 3.62 M097500300056
19.11 29.60 3.29 M097500300057
19.51 24.28 2.79 M097500300058
20.11 22.03 2.58 M097500300059
20.31 19.22 2.18 M097500300060
20.71 15.44 1.88 M097500300061
21.11 13.19 1.71 M097500300062
21.51 12.69 2.04 M097500300063
21.91 10.52 1.91 M097500300064
22.31 10.62 1.92 M097500300065
22.71 10.90 1.57 M097500300066
23.11 10.77 1.76 M097500300067
23.51 10.12 1.91 M097500300068
23.91 9.49 1.88 M097500300069
24.31 9.13 1.78 M097500300070
24.71 8.82 1.69 M097500300071
25.31 5.70 1.40 M097500300072
25.91 5.87 1.46 M097500300073
26.51 7.04 1.52 M097500300074
27.11 3.85 1.07 M097500300075
27.71 3.43 1.12 M097500300076
28.31 4.89 1.15 M097500300077
29.51 3.75 1.72 M097500300078
ENDDATA 52 0 M097500300079
ENDSUBENT 78 0 M097500399999
SUBENT M0975004 20190121 M099M097500400001
BIB 4 20 M097500400002
REACTION (64-GD-160(G,2N)64-GD-158,,SIG,,,EVAL) M097500400003
ANALYSIS The contribution of partial reaction (g,2n) cross M097500400004
section into the experimental total neutron yield M097500400005
reaction (g,xn) cross section obtained using M097500400006
quasimonoenergetic annihilation photons at Livermore M097500400007
(USA) was evaluated using specially theoretically M097500400008
calculated transitional multiplicity function - M097500400009
ratio M097500400010
F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M097500400011
by the way M097500400012
SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M097500400013
REL-REF (R,L0016006,B.L.Berman+,J,PR,185,1576,1969) M097500400014
Experimental data for the total neutron yield M097500400015
reaction (g,xn) cross section. M097500400016
(E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097500400017
Theoretical preequilibrium model of photonuclear M097500400018
reactions based on the Fermi gas densities. M097500400019
STATUS (TABLE) Data plotted in Fig. 3. M097500400020
(DEP,L0016006) M097500400021
The neutron yield reaction (g,xn) cross section. M097500400022
ENDBIB 20 0 M097500400023
NOCOMMON 0 0 M097500400024
DATA 3 35 M097500400025
EN DATA DATA-ERR M097500400026
MEV MB MB M097500400027
13.91 8.07 0.86 M097500400028
14.31 55.91 5.80 M097500400029
14.71 96.88 10.01 M097500400030
15.11 134.40 14.18 M097500400031
15.51 141.86 15.02 M097500400032
15.91 163.39 16.62 M097500400033
16.31 167.38 17.26 M097500400034
16.71 164.87 17.73 M097500400035
17.11 153.79 16.07 M097500400036
17.51 147.53 15.50 M097500400037
17.91 126.12 13.44 M097500400038
18.31 116.10 12.48 M097500400039
18.71 102.40 11.12 M097500400040
19.11 95.71 10.64 M097500400041
19.51 81.95 9.42 M097500400042
20.11 77.08 9.03 M097500400043
20.31 67.55 7.69 M097500400044
20.71 54.74 6.67 M097500400045
21.11 47.09 6.12 M097500400046
21.51 45.47 7.31 M097500400047
21.91 38.23 6.95 M097500400048
22.31 38.80 7.03 M097500400049
22.71 38.46 5.57 M097500400050
23.11 35.11 5.76 M097500400051
23.51 29.76 5.63 M097500400052
23.91 24.70 4.89 M097500400053
24.31 21.23 4.14 M097500400054
24.71 18.40 3.54 M097500400055
25.31 10.12 2.49 M097500400056
25.91 9.19 2.29 M097500400057
26.51 9.94 2.14 M097500400058
27.11 5.07 1.41 M097500400059
27.71 4.31 1.41 M097500400060
28.31 5.95 1.40 M097500400061
29.51 4.32 1.98 M097500400062
ENDDATA 37 0 M097500400063
ENDSUBENT 62 0 M097500499999
SUBENT M0975005 20190121 M099M097500500001
BIB 4 20 M097500500002
REACTION (64-GD-160(G,3N)64-GD-157,,SIG,,,EVAL) M097500500003
ANALYSIS The contribution of partial reaction (g,3n) cross M097500500004
section into the experimental total neutron yield M097500500005
reaction (g,xn) cross section obtained using M097500500006
quasimonoenergetic annihilation photons at Livermore M097500500007
(USA) was evaluated using specially theoretically M097500500008
calculated transitional multiplicity function - M097500500009
ratio M097500500010
F3-theor = SIG-theor(g,3n)/SIG-theor(g,xn) M097500500011
by the way M097500500012
SIG-eval(g,3n) = (F2-theor)x(SIG-exp(g,xn)). M097500500013
REL-REF (R,L0016006,B.L.Berman+,J,PR,185,1576,1969) M097500500014
Experimental data for the total neutron yield M097500500015
reaction (g,xn) cross section. M097500500016
(E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097500500017
Theoretical preequilibrium model of photonuclear M097500500018
reactions based on the Fermi gas densities. M097500500019
STATUS (TABLE) Data plotted in Fig. 3. M097500500020
(DEP,L0016006) M097500500021
The neutron yield reaction (g,xn) cross section. M097500500022
ENDBIB 20 0 M097500500023
NOCOMMON 0 0 M097500500024
DATA 3 14 M097500500025
EN DATA DATA-ERR M097500500026
MEV MB MB M097500500027
22.31 0.41 0.07 M097500500028
22.71 2.35 0.34 M097500500029
23.11 5.89 0.96 M097500500030
23.51 9.81 1.85 M097500500031
23.91 13.35 2.64 M097500500032
24.31 16.74 3.26 M097500500033
24.71 19.75 3.80 M097500500034
25.31 15.48 3.82 M097500500035
25.91 17.85 4.45 M097500500036
26.51 22.52 4.86 M097500500037
27.11 13.06 3.65 M097500500038
27.71 12.81 4.19 M097500500039
28.31 20.40 4.80 M097500500040
29.51 18.64 8.55 M097500500041
ENDDATA 16 0 M097500500042
ENDSUBENT 41 0 M097500599999
SUBENT M0975006 20190121 M099M097500600001
BIB 3 4 M097500600002
REACTION (64-GD-160(G,X)0-NN-1,UNW,INT,,,EVAL) M097500600003
ANALYSIS Integration of evaluated cross section. M097500600004
STATUS (DEP,M0975002) Evaluated cross section. M097500600005
(TABLE) Data from Table 2. M097500600006
ENDBIB 4 0 M097500600007
NOCOMMON 0 0 M097500600008
DATA 3 39 M097500600009
EN-MAX DATA DATA-ERR M097500600010
MEV MB*MEV MB*MEV M097500600011
13.4 754.93 27.58 M097500600012
21.3 2235.71 40.62 M097500600013
30.0 2569.06 43.48 M097500600014
ENDDATA 5 0 M097500600015
ENDSUBENT 14 0 M097500699999
SUBENT M0975007 20190121 M099M097500700001
BIB 3 5 M097500700002
REACTION ((64-GD-160(G,N)64-GD-159,,INT,,,EVAL)+ M097500700003
(64-GD-160(G,N+P)63-EU-158,,INT,,,EVAL)) M097500700004
ANALYSIS Integration of evaluated cross section. M097500700005
STATUS (DEP,M0975003) Evaluated cross section. M097500700006
(TABLE) Data from Table 2. M097500700007
ENDBIB 5 0 M097500700008
NOCOMMON 0 0 M097500700009
DATA 3 39 M097500700010
EN-MAX DATA DATA-ERR M097500700011
MEV MB*MEV MB*MEV M097500700012
13.4 754.93 27.58 M097500700013
21.3 1433.11 34.53 M097500700014
30.0 1495.69 34.72 M097500700015
ENDDATA 5 0 M097500700016
ENDSUBENT 15 0 M097500799999
SUBENT M0975008 20190121 M099M097500800001
BIB 3 4 M097500800002
REACTION (64-GD-160(G,2N)64-GD-158,,INT,,,EVAL) M097500800003
ANALYSIS Integration of evaluated cross section. M097500800004
STATUS (DEP,M0975004) Evaluated cross section. M097500800005
(TABLE) Data from Table 2. M097500800006
ENDBIB 4 0 M097500800007
NOCOMMON 0 0 M097500800008
DATA 3 29 M097500800009
EN-MAX DATA DATA-ERR M097500800010
MEV MB*MEV MB*MEV M097500800011
21.3 802.60 34.53 M097500800012
30.0 954.28 22.83 M097500800013
ENDDATA 4 0 M097500800014
ENDSUBENT 13 0 M097500899999
SUBENT M0975009 20190121 M099M097500900001
BIB 3 4 M097500900002
REACTION (64-GD-160(G,3N)64-GD-157,,INT,,,EVAL) M097500900003
ANALYSIS Integration of evaluated cross section. M097500900004
STATUS (DEP,M0975005) Evaluated cross section. M097500900005
(TABLE) Data from Table 2. M097500900006
ENDBIB 4 0 M097500900007
NOCOMMON 0 0 M097500900008
DATA 3 19 M097500900009
EN-MAX DATA DATA-ERR M097500900010
MEV MB*MEV MB*MEV M097500900011
30.0 119.10 12.78 M097500900012
ENDDATA 3 0 M097500900013
ENDSUBENT 12 0 M097500999999
ENDENTRY 9 0 M097599999999