ENTRY M0938 20170925 M091M093800000001 SUBENT M0938001 20170925 M091M093800100001 BIB 9 36 M093800100002 TITLE Cross sections of the photoneutron reaction for 141Pr M093800100003 and 186W nuclei, estimated from physical criteria M093800100004 of data reliability. M093800100005 AUTHOR (V.V.Varlamov,V.N.Orlin,N.N.Peskov) M093800100006 REFERENCE (J,IZV,81,744,2017) M093800100007 #doi:10.7868/S0367676517060254 M093800100008 (J,BAS,81,670,2017) M093800100009 #doi:10.3103/S1062873817060259 M093800100010 English translation of IZV,81,744,2017. M093800100011 INSTITUTE (4RUSMOS) M093800100012 INC-SOURCE (QMPH,ARAD) M093800100013 ANALYSIS The joint analysis of data for total (g,xn) and M093800100014 partial (g,n) and (g,2n) reactions obtained in M093800100015 various experiments was carried out. The new M093800100016 approach to analysis of systematic disagreements M093800100017 between data was proposed on the base of new M093800100018 criteria of systematic uncertainties presence - M093800100019 specially proposed transitional multiplicity M093800100020 functions M093800100021 Fi-theor = SIG(g,in)/SIG(g,xn). M093800100022 Using these functions calculated in the frame of M093800100023 combined photonuclear reaction model new reliable M093800100024 and free from problems of neutron multiplicity M093800100025 sorting data for photoneutron partial reactions M093800100026 cross sections M093800100027 SIG-eval(g,in) = Fi-theor x SIG-exp(g,xn) M093800100028 were evaluated using experimental neutron yield M093800100029 reaction cross sections SIG-exp(g,xn). M093800100030 ERR-ANALYS (DATA-ERR) Root-mean-square errors. M093800100031 STATUS (TABLE,APRVD) Approved by V.Varlamov. M093800100032 HISTORY (20170628C) Data were compiled at the Russia MSU SINP M093800100033 CDFE by V.Varlamov. M093800100034 (20170925A) Corrected by V.Varlamov: ANALYSIS in M093800100035 SUBENTs 002 - 006, 008, 009, REACTION in SUBENTs 005 M093800100036 and 009, STATUS in SUBENTs 007 - 009 and REL-REF in M093800100037 SUBENTs 003 - 005, 007 - 009. M093800100038 ENDBIB 36 0 M093800100039 NOCOMMON 0 0 M093800100040 ENDSUBENT 39 0 M093800199999 SUBENT M0938002 20170925 M091M093800200001 BIB 4 11 M093800200002 REACTION (59-PR-141(G,X)0-NN-1,UNW,SIG,,,EVAL) M093800200003 ANALYSIS The total neutron reaction cross section obtained as M093800200004 sum: SIG(g,sn) = SIG(g,n) + SIG(g,2n) + SIG(g,3n). M093800200005 STATUS Data plotted in Fig. 4. M093800200006 (DEP,M0938003) M093800200007 Evaluated (g,n) reaction cross section. M093800200008 (DEP,M0938004) M093800200009 Evaluated (g,2n) reaction cross section. M093800200010 (DEP,M0938005) M093800200011 Evaluated (g,3n) reaction cross section. M093800200012 HISTORY (20170925U) Corrected by V.Varlamov: ANALYSIS. M093800200013 ENDBIB 11 0 M093800200014 NOCOMMON 0 0 M093800200015 DATA 3 68 M093800200016 EN DATA DATA-ERR M093800200017 MEV MB MB M093800200018 8.8 0.00 0.34 M093800200019 9.4 1.73 1.46 M093800200020 9.7 21.30 6.08 M093800200021 10.0 34.25 7.79 M093800200022 10.3 46.86 10.25 M093800200023 10.6 44.83 9.94 M093800200024 10.9 60.79 13.18 M093800200025 11.2 67.62 13.66 M093800200026 11.6 76.86 15.88 M093800200027 11.9 84.45 17.44 M093800200028 12.2 104.60 21.35 M093800200029 12.5 127.90 25.85 M093800200030 12.8 144.00 28.98 M093800200031 13.1 167.90 33.60 M093800200032 13.4 200.50 39.93 M093800200033 13.7 230.70 45.83 M093800200034 14.0 259.30 51.26 M093800200035 14.3 298.70 58.55 M093800200036 14.7 324.30 61.54 M093800200037 15.0 346.30 68.82 M093800200038 15.3 341.60 62.59 M093800200039 15.6 330.80 64.69 M093800200040 15.9 303.00 59.93 M093800200041 16.2 276.70 55.19 M093800200042 16.5 251.20 54.44 M093800200043 16.8 220.30 45.26 M093800200044 17.1 194.80 41.45 M093800200045 17.4 176.00 38.46 M093800200046 17.8 161.90 36.34 M093800200047 18.1 146.10 34.32 M093800200048 18.4 122.80 30.55 M093800200049 18.7 103.90 26.98 M093800200050 19.0 99.64 27.06 M093800200051 19.3 100.80 27.74 M093800200052 19.6 78.42 22.73 M093800200053 19.9 90.15 25.35 M093800200054 20.2 79.44 22.91 M093800200055 20.5 73.60 22.75 M093800200056 20.9 56.42 18.83 M093800200057 21.2 55.47 18.83 M093800200058 21.5 56.42 19.34 M093800200059 21.8 57.14 19.78 M093800200060 22.1 51.20 18.57 M093800200061 22.4 51.26 18.83 M093800200062 22.7 43.40 17.06 M093800200063 23.0 48.29 18.45 M093800200064 23.3 40.30 16.72 M093800200065 23.6 35.62 15.68 M093800200066 23.9 45.45 18.29 M093800200067 24.3 41.91 17.62 M093800200068 24.6 30.04 15.69 M093800200069 24.9 24.29 14.28 M093800200070 25.2 33.42 19.61 M093800200071 25.5 40.43 21.16 M093800200072 25.8 44.02 23.58 M093800200073 26.1 32.07 19.79 M093800200074 26.4 35.50 20.18 M093800200075 26.7 31.88 20.04 M093800200076 27.1 32.31 19.38 M093800200077 27.4 38.52 23.04 M093800200078 27.7 32.18 19.93 M093800200079 28.0 36.50 23.58 M093800200080 28.3 21.08 17.45 M093800200081 28.6 16.95 16.90 M093800200082 28.9 18.91 16.84 M093800200083 29.2 11.42 15.63 M093800200084 29.5 14.75 18.07 M093800200085 29.8 29.94 25.01 M093800200086 ENDDATA 70 0 M093800200087 ENDSUBENT 86 0 M093800299999 SUBENT M0938003 20170925 M091M093800300001 BIB 5 29 M093800300002 REACTION ((59-PR-141(G,N)59-PR-140,,SIG,,,EVAL)+ M093800300003 (59-PR-141(G,N+P)58-CE-139,,SIG,,,EVAL)) M093800300004 ANALYSIS The contribution of partial reaction (g,n) cross M093800300005 section into the experimental total neutron yield M093800300006 reaction (g,xn) cross section obtained using M093800300007 quasimonoenergetic annihilation photons at Livermore M093800300008 (USA) was evaluated using specially theoretically M093800300009 calculated transitional multiplicity function - M093800300010 ratio M093800300011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M093800300012 by the way M093800300013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M093800300014 For the better agreement between the experimental M093800300015 neutron yield cross section and the correspondent M093800300016 theoretical one the first was shifted in 0.01 MeV up M093800300017 to larger energies and multiplied by 1.04 and the M093800300018 second one was shifted in 0.09 MeV up to larger M093800300019 energies and multiplied by 0.90. M093800300020 REL-REF (R,L0009010,R.L.Bramblett+,J,PR,148,1198,1966) M093800300021 Experimental data for the total neutron yield M093800300022 reaction (g,xn)= cross section. M093800300023 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M093800300024 Theoretical preequilibrium model of photonuclear M093800300025 reactions based on the Fermi gas densities. M093800300026 STATUS Data plotted in Fig. 4. M093800300027 (DEP,L0009010) M093800300028 The neutron yield reaction (g,xn) = (g,n) + 2(g,2n) M093800300029 + 3(g,3n) cross section. M093800300030 HISTORY (20170925U) Corrected by V.Varlamov: REL-REF, STATUS. M093800300031 ENDBIB 29 0 M093800300032 NOCOMMON 0 0 M093800300033 DATA 3 68 M093800300034 EN DATA DATA-ERR M093800300035 MEV MB MB M093800300036 8.8 0.00 0.31 M093800300037 9.4 1.73 1.37 M093800300038 9.7 21.30 5.90 M093800300039 10.0 34.25 7.60 M093800300040 10.3 46.86 10.00 M093800300041 10.6 44.83 9.70 M093800300042 10.9 60.79 12.84 M093800300043 11.2 67.62 13.28 M093800300044 11.6 76.86 15.46 M093800300045 11.9 84.45 16.97 M093800300046 12.2 104.60 20.77 M093800300047 12.5 127.90 25.14 M093800300048 12.8 144.00 28.19 M093800300049 13.1 167.90 32.67 M093800300050 13.4 200.50 38.82 M093800300051 13.7 230.70 44.56 M093800300052 14.0 259.30 49.82 M093800300053 14.3 298.70 56.91 M093800300054 14.7 324.30 59.83 M093800300055 15.0 346.30 67.00 M093800300056 15.3 341.60 60.81 M093800300057 15.6 330.80 62.88 M093800300058 15.9 303.00 58.26 M093800300059 16.2 276.70 53.67 M093800300060 16.5 251.20 53.05 M093800300061 16.8 220.30 44.04 M093800300062 17.1 194.80 40.36 M093800300063 17.4 174.60 37.34 M093800300064 17.8 154.00 34.26 M093800300065 18.1 127.50 30.63 M093800300066 18.4 94.70 25.36 M093800300067 18.7 69.01 20.74 M093800300068 19.0 56.50 19.33 M093800300069 19.3 49.10 18.72 M093800300070 19.6 33.25 14.33 M093800300071 19.9 34.11 15.47 M093800300072 20.2 27.72 13.45 M093800300073 20.5 23.72 13.04 M093800300074 20.9 17.14 10.30 M093800300075 21.2 16.09 10.11 M093800300076 21.5 15.76 10.24 M093800300077 21.8 15.44 10.35 M093800300078 22.1 13.41 9.43 M093800300079 22.4 13.08 9.45 M093800300080 22.7 10.82 8.24 M093800300081 23.0 11.77 8.99 M093800300082 23.3 9.61 7.78 M093800300083 23.6 8.34 7.06 M093800300084 23.9 10.46 8.57 M093800300085 24.3 9.51 8.08 M093800300086 24.6 6.78 6.89 M093800300087 24.9 5.41 5.86 M093800300088 25.2 7.39 9.04 M093800300089 25.5 8.87 9.93 M093800300090 25.8 9.64 11.34 M093800300091 26.1 7.01 8.66 M093800300092 26.4 7.75 9.27 M093800300093 26.7 6.96 8.80 M093800300094 27.1 7.05 8.54 M093800300095 27.4 8.42 10.50 M093800300096 27.7 7.04 8.58 M093800300097 28.0 8.01 10.41 M093800300098 28.3 4.63 6.51 M093800300099 28.6 3.74 6.23 M093800300100 28.9 4.18 6.08 M093800300101 29.2 2.55 5.25 M093800300102 29.5 3.29 6.29 M093800300103 29.8 6.66 10.26 M093800300104 ENDDATA 70 0 M093800300105 ENDSUBENT 104 0 M093800399999 SUBENT M0938004 20170925 M091M093800400001 BIB 5 30 M093800400002 REACTION ((59-PR-141(G,2N)59-PR-139,,SIG,,,EVAL)+ M093800400003 (59-PR-141(G,2N+P)58-CE-138,,SIG,,,EVAL)) M093800400004 ANALYSIS The contribution of partial reaction (g,2n) cross M093800400005 section into the experimental total neutron yield M093800400006 reaction (g,xn) = (g,n) + 2(g,2n) cross section M093800400007 obtained using quasimonoenergetic annihilation M093800400008 photons at Livermore (USA) was evaluated using M093800400009 specially theoretically calculated transitional M093800400010 multiplicity function - ratio M093800400011 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M093800400012 by the way M093800400013 SIG-eval(g,n) = (F2-theor)x(SIG-exp(g,xn)). M093800400014 For the better agreement between the experimental M093800400015 neutron yield cross section and the correspondent M093800400016 theoretical one the first was shifted in 0.01 MeV up M093800400017 to larger energies and multiplied by 1.04 and the M093800400018 second one was shifted in 0.09 MeV up to larger M093800400019 energies and multiplied by 0.90. M093800400020 REL-REF (R,L0009010,R.L.Bramblett+,J,PR,148,1198,1966) M093800400021 Experimental data for the total neutron yield M093800400022 reaction (g,xn) cross section. M093800400023 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M093800400024 Theoretical preequilibrium model of photonuclear M093800400025 reactions based on the Fermi gas densities. M093800400026 STATUS Data plotted in Fig. 3. M093800400027 (DEP,L0009010) M093800400028 The neutron yield reaction (g,xn) = (g,n) + 2(g,2n) M093800400029 + 3(g,3n) cross section. M093800400030 HISTORY (20170925U) Corrected by V.Varlamov: ANALYSIS, M093800400031 REL-REF and STATUS. M093800400032 ENDBIB 30 0 M093800400033 NOCOMMON 0 0 M093800400034 DATA 3 42 M093800400035 EN DATA DATA-ERR M093800400036 MEV MB MB M093800400037 17.1 0.05 1.05 M093800400038 17.4 1.40 1.09 M093800400039 17.8 7.93 2.04 M093800400040 18.1 18.62 3.66 M093800400041 18.4 28.09 5.16 M093800400042 18.7 34.88 6.22 M093800400043 19.0 43.14 7.71 M093800400044 19.3 51.69 8.99 M093800400045 19.6 45.17 8.38 M093800400046 19.9 56.04 9.85 M093800400047 20.2 51.72 9.44 M093800400048 20.5 49.88 9.68 M093800400049 20.9 39.28 8.52 M093800400050 21.2 39.38 8.71 M093800400051 21.5 40.66 9.09 M093800400052 21.8 41.69 9.42 M093800400053 22.1 37.79 9.13 M093800400054 22.4 38.18 9.37 M093800400055 22.7 32.57 8.81 M093800400056 23.0 36.53 9.45 M093800400057 23.3 30.69 8.93 M093800400058 23.6 27.29 8.61 M093800400059 23.9 34.99 9.71 M093800400060 24.3 32.40 9.53 M093800400061 24.6 23.26 8.79 M093800400062 24.9 18.87 8.41 M093800400063 25.2 26.02 10.56 M093800400064 25.5 31.56 11.22 M093800400065 25.8 34.38 12.23 M093800400066 26.1 25.07 11.12 M093800400067 26.4 27.74 10.89 M093800400068 26.7 24.92 11.22 M093800400069 27.1 25.25 10.83 M093800400070 27.4 30.10 12.52 M093800400071 27.7 25.10 11.33 M093800400072 28.0 28.25 13.05 M093800400073 28.3 16.17 10.76 M093800400074 28.6 12.62 10.19 M093800400075 28.9 13.75 10.07 M093800400076 29.2 7.81 9.14 M093800400077 29.5 9.95 10.27 M093800400078 29.8 17.39 11.10 M093800400079 ENDDATA 44 0 M093800400080 ENDSUBENT 79 0 M093800499999 SUBENT M0938005 20170925 M091M093800500001 BIB 5 29 M093800500002 REACTION (59-PR-141(G,3N)59-PR-138,,SIG,,,EVAL) M093800500003 ANALYSIS The contribution of partial reaction (g,3n) cross M093800500004 section into the experimental total neutron yield M093800500005 reaction (g,xn) = (g,n) + 2(g,2n) cross section M093800500006 obtained using quasimonoenergetic annihilation M093800500007 photons at Livermore (USA) was evaluated using M093800500008 specially theoretically calculated transitional M093800500009 multiplicity function - ratio M093800500010 F3-theor = SIG-theor(g,3n)/SIG-theor(g,xn) M093800500011 by the way M093800500012 SIG-eval(g,3n) = (F3-theor)x(SIG-exp(g,xn)). M093800500013 For the better agreement between the experimental M093800500014 neutron yield cross section and the correspondent M093800500015 theoretical one the first was shifted in 0.01 MeV up M093800500016 to larger energies and multiplied by 1.04 and the M093800500017 second one was shifted in 0.09 MeV up to larger M093800500018 energies and multiplied by 0.90. M093800500019 REL-REF (R,L0009010,R.L.Bramblett+,J,PR,148,1198,1966) M093800500020 Experimental data for the total neutron yield M093800500021 reaction (g,xn) cross section. M093800500022 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M093800500023 Theoretical preequilibrium model of photonuclear M093800500024 reactions based on the Fermi gas densities. M093800500025 STATUS Data plotted in Fig. 3. M093800500026 (DEP,L0009010) M093800500027 The neutron yield reaction (g,xn) = (g,n) + 2(g,2n) M093800500028 + 3(g,3n) cross section. M093800500029 HISTORY (20170925A) Corrected by V.Varlamov: ANALYSIS, M093800500030 REL-REF, STATUS and REACTION. M093800500031 ENDBIB 29 0 M093800500032 NOCOMMON 0 0 M093800500033 DATA 3 8 M093800500034 EN DATA DATA-ERR M093800500035 MEV MB MB M093800500036 27.7 0.04 0.03 M093800500037 28.0 0.24 0.12 M093800500038 28.3 0.27 0.18 M093800500039 28.6 0.60 0.48 M093800500040 28.9 0.97 0.69 M093800500041 29.2 1.06 1.23 M093800500042 29.5 1.50 1.51 M093800500043 29.8 5.90 3.65 M093800500044 ENDDATA 10 0 M093800500045 ENDSUBENT 44 0 M093800599999 SUBENT M0938006 20170925 M091M093800600001 BIB 4 11 M093800600002 REACTION (74-W-186(G,X)0-NN-1,UNW,SIG,,,EVAL) M093800600003 ANALYSIS The total neutron reaction cross section obtained as M093800600004 sum: SIG(g,sn) = SIG(g,n) + SIG(g,2n) + SIG(g,3n). M093800600005 STATUS Data plotted in Fig. 7. M093800600006 (DEP,M0938007) M093800600007 Evaluated (g,n) reaction cross section. M093800600008 (DEP,M0938008) M093800600009 Evaluated (g,2n) reaction cross section. M093800600010 (DEP,M0938009) M093800600011 Evaluated (g,3n) reaction cross section. M093800600012 HISTORY (20170925U) Corrected by V.Varlamov: ANALYSIS. M093800600013 ENDBIB 11 0 M093800600014 NOCOMMON 0 0 M093800600015 DATA 3 76 M093800600016 EN DATA DATA-ERR M093800600017 MEV MB MB M093800600018 9.10 46.21 9.89 M093800600019 9.41 52.23 10.66 M093800600020 9.72 51.67 11.62 M093800600021 10.03 65.43 11.85 M093800600022 10.34 80.25 14.18 M093800600023 10.65 97.51 16.70 M093800600024 10.96 136.90 23.77 M093800600025 11.27 167.80 28.32 M093800600026 11.42 196.20 32.47 M093800600027 11.57 217.80 33.52 M093800600028 11.73 243.80 38.66 M093800600029 11.89 277.60 41.83 M093800600030 12.04 302.80 47.14 M093800600031 12.19 336.70 50.28 M093800600032 12.35 369.20 56.77 M093800600033 12.50 366.40 54.68 M093800600034 12.66 391.30 59.98 M093800600035 12.81 394.00 58.73 M093800600036 12.97 385.90 59.43 M093800600037 13.12 399.50 59.92 M093800600038 13.28 409.80 63.58 M093800600039 13.43 405.90 62.03 M093800600040 13.59 398.40 64.00 M093800600041 13.74 406.40 64.21 M093800600042 13.90 408.60 68.30 M093800600043 14.05 401.60 66.73 M093800600044 14.21 387.10 67.48 M093800600045 14.36 391.90 67.24 M093800600046 14.52 388.50 69.89 M093800600047 14.67 392.10 69.09 M093800600048 14.83 396.60 73.07 M093800600049 14.98 390.60 70.25 M093800600050 15.14 373.40 69.98 M093800600051 15.29 371.00 67.81 M093800600052 15.45 362.80 69.69 M093800600053 15.60 347.00 64.38 M093800600054 15.76 360.30 70.26 M093800600055 15.91 329.90 62.14 M093800600056 16.07 313.60 62.70 M093800600057 16.22 304.80 58.01 M093800600058 16.53 265.10 52.30 M093800600059 16.84 233.70 46.75 M093800600060 17.15 218.40 43.81 M093800600061 17.46 201.10 40.66 M093800600062 17.77 173.30 35.62 M093800600063 18.08 153.00 32.46 M093800600064 18.39 141.30 30.60 M093800600065 18.70 119.80 26.76 M093800600066 19.01 117.20 26.23 M093800600067 19.32 100.20 23.20 M093800600068 19.63 88.05 21.45 M093800600069 19.94 84.90 20.17 M093800600070 20.25 86.31 21.00 M093800600071 20.56 72.55 20.52 M093800600072 20.87 73.42 20.98 M093800600073 21.18 67.97 21.01 M093800600074 21.48 57.48 21.31 M093800600075 21.80 49.44 19.96 M093800600076 22.11 56.98 17.90 M093800600077 22.41 35.78 14.07 M093800600078 22.72 48.88 16.40 M093800600079 23.03 41.61 15.23 M093800600080 23.34 52.56 18.73 M093800600081 23.65 44.16 15.70 M093800600082 23.96 41.28 15.89 M093800600083 24.27 48.47 16.74 M093800600084 24.58 45.60 17.04 M093800600085 24.89 44.63 17.38 M093800600086 25.20 45.78 21.24 M093800600087 25.51 41.79 16.64 M093800600088 25.82 39.78 20.20 M093800600089 26.13 48.09 19.02 M093800600090 26.59 34.59 16.01 M093800600091 27.22 34.08 14.59 M093800600092 27.83 43.29 19.40 M093800600093 28.45 33.12 16.59 M093800600094 ENDDATA 78 0 M093800600095 ENDSUBENT 94 0 M093800699999 SUBENT M0938007 20170925 M091M093800700001 BIB 5 27 M093800700002 REACTION ((74-W-186(G,N)74-W-185,,SIG,,,EVAL)+ M093800700003 (74-W-186(G,N+P)73-TA-184,,SIG,,,EVAL)) M093800700004 ANALYSIS The contribution of partial reaction (g,n) cross M093800700005 section into the experimental total neutron yield M093800700006 reaction (g,xn) cross section obtained using M093800700007 quasimonoenergetic annihilation photons at Livermore M093800700008 (USA) was evaluated using specially theoretically M093800700009 calculated transitional multiplicity function - M093800700010 ratio M093800700011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M093800700012 by the way M093800700013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M093800700014 For the better agreement with the experimental M093800700015 neutron yield cross section the correspondent M093800700016 theoretical one was shifted in 0.24 MeV up to larger M093800700017 energies and multiplied by 0.996. M093800700018 REL-REF (R,L0016014,B.L.Berman+,J,PR,185,1576,1969) M093800700019 Experimental data for the total neutron yield M093800700020 reaction (g,xn) cross section. M093800700021 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M093800700022 Theoretical preequilibrium model of photonuclear M093800700023 reactions based on the Fermi gas densities. M093800700024 STATUS Data plotted in Fig. 7. M093800700025 (DEP,L0016014) M093800700026 The neutron yield reaction (g,xn) = (g,n) + 2(g,2n) M093800700027 + 3(g,3n) cross section. M093800700028 HISTORY (20170925U) Corrected by V.Varlamov: REL-REF, STATUS. M093800700029 ENDBIB 27 0 M093800700030 NOCOMMON 0 0 M093800700031 DATA 3 76 M093800700032 EN DATA DATA-ERR M093800700033 MEV MB MB M093800700034 9.10 46.21 8.79 M093800700035 9.41 52.23 9.41 M093800700036 9.72 51.67 10.38 M093800700037 10.03 65.43 10.28 M093800700038 10.34 80.25 12.25 M093800700039 10.65 97.51 14.36 M093800700040 10.96 136.90 20.47 M093800700041 11.27 167.80 24.28 M093800700042 11.42 196.20 27.74 M093800700043 11.57 217.80 28.26 M093800700044 11.73 243.80 32.80 M093800700045 11.89 277.60 35.12 M093800700046 12.04 302.80 39.87 M093800700047 12.19 336.70 42.14 M093800700048 12.35 369.20 47.92 M093800700049 12.50 366.40 45.81 M093800700050 12.66 391.30 50.61 M093800700051 12.81 394.00 49.17 M093800700052 12.97 385.40 50.17 M093800700053 13.12 397.50 50.09 M093800700054 13.28 403.00 53.11 M093800700055 13.43 388.80 50.45 M093800700056 13.59 363.20 50.09 M093800700057 13.74 344.90 46.93 M093800700058 13.90 317.40 46.95 M093800700059 14.05 283.40 42.62 M093800700060 14.21 247.80 40.65 M093800700061 14.36 228.60 38.27 M093800700062 14.52 208.00 37.96 M093800700063 14.67 194.20 36.14 M093800700064 14.83 183.10 36.81 M093800700065 14.98 169.00 34.55 M093800700066 15.14 151.90 33.28 M093800700067 15.29 142.10 31.69 M093800700068 15.45 131.00 31.47 M093800700069 15.60 118.30 28.75 M093800700070 15.76 116.10 30.33 M093800700071 15.91 100.60 26.65 M093800700072 16.07 90.68 25.95 M093800700073 16.22 83.85 24.04 M093800700074 16.53 66.64 20.86 M093800700075 16.84 54.50 18.17 M093800700076 17.15 47.78 16.73 M093800700077 17.46 41.79 15.27 M093800700078 17.77 34.57 13.15 M093800700079 18.08 29.52 11.72 M093800700080 18.39 26.58 10.87 M093800700081 18.70 22.06 9.32 M093800700082 19.01 21.24 9.10 M093800700083 19.32 17.93 7.89 M093800700084 19.63 15.61 7.09 M093800700085 19.94 14.96 6.54 M093800700086 20.25 15.16 6.78 M093800700087 20.56 12.75 6.32 M093800700088 20.87 12.97 6.50 M093800700089 21.18 12.12 6.33 M093800700090 21.48 10.38 6.04 M093800700091 21.80 9.06 5.56 M093800700092 22.11 10.62 5.56 M093800700093 22.41 6.76 4.08 M093800700094 22.72 9.32 5.11 M093800700095 23.03 7.96 4.64 M093800700096 23.34 10.04 5.81 M093800700097 23.65 8.39 4.91 M093800700098 23.96 7.81 4.84 M093800700099 24.27 9.16 5.35 M093800700100 24.58 8.61 5.41 M093800700101 24.89 8.41 5.65 M093800700102 25.20 8.57 7.09 M093800700103 25.51 7.69 5.36 M093800700104 25.82 7.13 6.62 M093800700105 26.13 8.38 6.05 M093800700106 26.59 5.80 5.21 M093800700107 27.22 5.43 4.82 M093800700108 27.83 6.66 6.13 M093800700109 28.45 5.01 4.86 M093800700110 ENDDATA 78 0 M093800700111 ENDSUBENT 110 0 M093800799999 SUBENT M0938008 20170925 M091M093800800001 BIB 5 28 M093800800002 REACTION ((74-W-186(G,2N)74-W-184,,SIG,,,EVAL)+ M093800800003 (74-W-186(G,2N+P)73-TA-183,,SIG,,,EVAL)) M093800800004 ANALYSIS The contribution of partial reaction (g,2n) cross M093800800005 section into the experimental total neutron yield M093800800006 reaction (g,xn) cross section obtained using M093800800007 quasimonoenergetic annihilation photons at Livermore M093800800008 (USA) was evaluated using specially theoretically M093800800009 calculated transitional multiplicity function - M093800800010 ratio M093800800011 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M093800800012 by the way M093800800013 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M093800800014 For the better agreement with the experimental M093800800015 neutron yield cross section the correspondent M093800800016 theoretical one was shifted in 0.24 MeV up to larger M093800800017 energies and multiplied by 0.996. M093800800018 REL-REF (R,L0016014,B.L.Berman+,J,PR,185,1576,1969) M093800800019 Experimental data for the total neutron yield M093800800020 reaction (g,xn) cross section. M093800800021 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M093800800022 Theoretical preequilibrium model of photonuclear M093800800023 reactions based on the Fermi gas densities. M093800800024 STATUS Data plotted in Fig. 7. M093800800025 (DEP,L0016014) M093800800026 The neutron yield reaction (g,xn) = (g,n) + 2(g,2n) M093800800027 + 3(g,3n) cross section. M093800800028 HISTORY (20170925U) Corrected by V.Varlamov: ANALYSIS, M093800800029 REL-REF, STATUS. M093800800030 ENDBIB 28 0 M093800800031 NOCOMMON 0 0 M093800800032 DATA 3 60 M093800800033 EN DATA DATA-ERR M093800800034 MEV MB MB M093800800035 12.66 0.01 9.04 M093800800036 12.81 0.06 9.22 M093800800037 12.97 0.44 8.94 M093800800038 13.12 2.03 9.49 M093800800039 13.28 6.75 10.12 M093800800040 13.43 17.13 11.22 M093800800041 13.59 35.18 13.55 M093800800042 13.74 61.57 16.88 M093800800043 13.90 91.15 20.92 M093800800044 14.05 118.20 23.66 M093800800045 14.21 139.30 26.38 M093800800046 14.36 163.30 28.49 M093800800047 14.52 180.50 31.45 M093800800048 14.67 197.90 32.44 M093800800049 14.83 213.50 35.73 M093800800050 14.98 221.70 35.17 M093800800051 15.14 221.60 36.20 M093800800052 15.29 228.90 35.60 M093800800053 15.45 231.80 37.72 M093800800054 15.60 228.80 35.13 M093800800055 15.76 244.30 39.41 M093800800056 15.91 229.30 35.02 M093800800057 16.07 222.90 36.30 M093800800058 16.22 220.90 33.52 M093800800059 16.53 198.50 31.04 M093800800060 16.84 179.20 28.23 M093800800061 17.15 170.60 26.75 M093800800062 17.46 159.30 25.08 M093800800063 17.77 138.70 22.20 M093800800064 18.08 123.50 20.51 M093800800065 18.39 114.80 19.51 M093800800066 18.70 97.72 17.26 M093800800067 19.01 95.95 16.95 M093800800068 19.32 82.28 15.15 M093800800069 19.63 72.44 14.22 M093800800070 19.94 69.94 13.51 M093800800071 20.25 71.15 14.10 M093800800072 20.56 59.79 14.08 M093800800073 20.87 60.36 14.35 M093800800074 21.18 55.25 14.46 M093800800075 21.48 45.41 14.73 M093800800076 21.80 37.11 13.34 M093800800077 22.11 39.83 10.88 M093800800078 22.41 22.98 8.20 M093800800079 22.72 28.58 8.74 M093800800080 23.03 22.08 7.59 M093800800081 23.34 25.25 8.67 M093800800082 23.65 19.23 6.79 M093800800083 23.96 16.32 6.43 M093800800084 24.27 17.46 6.42 M093800800085 24.58 15.14 6.21 M093800800086 24.89 13.81 6.14 M093800800087 25.20 12.84 7.17 M093800800088 25.51 11.00 5.40 M093800800089 25.82 9.63 6.35 M093800800090 26.13 10.96 5.75 M093800800091 26.59 7.23 4.76 M093800800092 27.22 6.30 4.22 M093800800093 27.83 7.21 5.27 M093800800094 28.45 5.09 4.13 M093800800095 ENDDATA 62 0 M093800800096 ENDSUBENT 95 0 M093800899999 SUBENT M0938009 20170925 M091M093800900001 BIB 5 27 M093800900002 REACTION (74-W-186(G,3N)74-W-183,,SIG,,,EVAL) M093800900003 ANALYSIS The contribution of partial reaction (g,3n) cross M093800900004 section into the experimental total neutron yield M093800900005 reaction (g,xn) = (g,n) + 2(g,2n) cross section M093800900006 obtained using quasimonoenergetic annihilation M093800900007 photons at Livermore (USA) was evaluated using M093800900008 specially theoretically calculated transitional M093800900009 multiplicity function - ratio M093800900010 F3-theor = SIG-theor(g,3n)/SIG-theor(g,xn) M093800900011 by the way M093800900012 SIG-eval(g,3n) = (F3-theor)x(SIG-exp(g,xn)). M093800900013 For the better agreement with the experimental M093800900014 neutron yield cross section the correspondent M093800900015 theoretical one was shifted in 0.24 MeV up to larger M093800900016 energies and multiplied by 0.996. M093800900017 REL-REF (R,L0016014,B.L.Berman+,J,PR,185,1576,1969) M093800900018 Experimental data for the total neutron yield M093800900019 reaction (g,xn) cross section. M093800900020 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M093800900021 Theoretical preequilibrium model of photonuclear M093800900022 reactions based on the Fermi gas densities. M093800900023 STATUS Data plotted in Fig. 3. M093800900024 (DEP,L0016014) M093800900025 The neutron yield reaction (g,xn) = (g,n) + 2(g,2n) M093800900026 + 3(g,3n) cross section. M093800900027 HISTORY (20170925A) Corrected by V.Varlamov: REACTION, M093800900028 ANALYSIS, REL-REF, STATUS. M093800900029 ENDBIB 27 0 M093800900030 NOCOMMON 0 0 M093800900031 DATA 3 22 M093800900032 EN DATA DATA-ERR M093800900033 MEV MB MB M093800900034 20.87 0.09 0.13 M093800900035 21.18 0.59 0.22 M093800900036 21.48 1.69 0.55 M093800900037 21.80 3.26 1.06 M093800900038 22.11 6.52 1.46 M093800900039 22.41 6.04 1.79 M093800900040 22.72 10.98 2.55 M093800900041 23.03 11.56 3.00 M093800900042 23.34 17.27 4.25 M093800900043 23.65 16.54 4.00 M093800900044 23.96 17.15 4.61 M093800900045 24.27 21.86 4.96 M093800900046 24.58 21.85 5.42 M093800900047 24.89 22.41 5.59 M093800900048 25.20 24.37 6.98 M093800900049 25.51 23.10 5.89 M093800900050 25.82 23.02 7.22 M093800900051 26.13 28.75 7.22 M093800900052 26.59 21.56 6.04 M093800900053 27.22 22.34 5.54 M093800900054 27.83 29.42 8.00 M093800900055 28.45 23.01 7.60 M093800900056 ENDDATA 24 0 M093800900057 ENDSUBENT 56 0 M093800999999 SUBENT M0938010 20170628 M090M093801000001 BIB 3 4 M093801000002 REACTION (59-PR-141(G,X)0-NN-1,UNW,INT,,,EVAL) M093801000003 ANALYSIS Integration of evaluated cross section. M093801000004 STATUS (DEP,M0938002) Evaluated cross section. M093801000005 Data from the Table 2. M093801000006 ENDBIB 4 0 M093801000007 NOCOMMON 0 0 M093801000008 DATA 3 3 M093801000009 EN-MAX DATA DATA-ERR M093801000010 MEV MB*MEV MB*MEV M093801000011 17.3 1412.3 75.0 M093801000012 27.1 2065.2 87.9 M093801000013 30.0 2136.5 90.8 M093801000014 ENDDATA 5 0 M093801000015 ENDSUBENT 14 0 M093801099999 SUBENT M0938011 20170628 M090M093801100001 BIB 3 5 M093801100002 REACTION ((59-PR-141(G,N)59-PR-140,,INT,,,EVAL)+ M093801100003 (59-PR-141(G,N+P)58-CE-139,,INT,,,EVAL)) M093801100004 ANALYSIS Integration of evaluated cross section. M093801100005 STATUS (DEP,M0938003) Evaluated cross section. M093801100006 Data from the Table 2. M093801100007 ENDBIB 5 0 M093801100008 NOCOMMON 0 0 M093801100009 DATA 3 3 M093801100010 EN-MAX DATA DATA-ERR M093801100011 MEV MB*MEV MB*MEV M093801100012 17.3 1412.3 72.9 M093801100013 27.1 1740.0 79.4 M093801100014 30.0 1755.7 79.9 M093801100015 ENDDATA 5 0 M093801100016 ENDSUBENT 15 0 M093801199999 SUBENT M0938012 20170628 M090M093801200001 BIB 3 5 M093801200002 REACTION ((59-PR-141(G,2N)59-PR-139,,INT,,,EVAL)+ M093801200003 (59-PR-141(G,2N+P)58-CE-138,,INT,,,EVAL)) M093801200004 ANALYSIS Integration of evaluated cross section. M093801200005 STATUS (DEP,M0938004) Evaluated cross section. M093801200006 Data from the Table 2. M093801200007 ENDBIB 5 0 M093801200008 NOCOMMON 0 0 M093801200009 DATA 3 2 M093801200010 EN-MAX DATA DATA-ERR M093801200011 MEV MB*MEV MB*MEV M093801200012 27.1 352.2 18.2 M093801200013 30.0 377.5 22.0 M093801200014 ENDDATA 4 0 M093801200015 ENDSUBENT 14 0 M093801299999 SUBENT M0938013 20170628 M090M093801300001 BIB 3 5 M093801300002 REACTION ((59-PR-141(G,3N)59-PR-138,,INT,,,EVAL)+ M093801300003 (59-PR-141(G,3N+P)58-CE-137,,INT,,,EVAL)) M093801300004 ANALYSIS Integration of evaluated cross section. M093801300005 STATUS (DEP,M0938005) Evaluated cross section. M093801300006 Data from the Table 2. M093801300007 ENDBIB 5 0 M093801300008 NOCOMMON 0 0 M093801300009 DATA 3 1 M093801300010 EN-MAX DATA DATA-ERR M093801300011 MEV MB*MEV MB*MEV M093801300012 30.0 112.30 11.27 M093801300013 ENDDATA 3 0 M093801300014 ENDSUBENT 13 0 M093801399999 SUBENT M0938014 20170628 M090M093801400001 BIB 3 4 M093801400002 REACTION (74-W-186(G,X)0-NN-1,UNW,INT,,,EVAL) M093801400003 ANALYSIS Integration of evaluated cross section. M093801400004 STATUS (DEP,M0938006) Evaluated cross section. M093801400005 Data from the Table 4. M093801400006 ENDBIB 4 0 M093801400007 NOCOMMON 0 0 M093801400008 DATA 3 3 M093801400009 EN-MAX DATA DATA-ERR M093801400010 MEV MB*MEV MB*MEV M093801400011 12.2 699.46 32.15 M093801400012 20.4 2606.99 77.97 M093801400013 28.5 2986.47 85.88 M093801400014 ENDDATA 5 0 M093801400015 ENDSUBENT 14 0 M093801499999 SUBENT M0938015 20170628 M090M093801500001 BIB 3 5 M093801500002 REACTION ((74-W-186(G,N)74-W-185,,INT,,,EVAL)+ M093801500003 (74-W-186(G,N+P)73-TA-184,,INT,,,EVAL)) M093801500004 ANALYSIS Integration of evaluated cross section. M093801500005 STATUS (DEP,M0938007) Evaluated cross section. M093801500006 Data from the Table 4. M093801500007 ENDBIB 5 0 M093801500008 NOCOMMON 0 0 M093801500009 DATA 3 3 M093801500010 EN-MAX DATA DATA-ERR M093801500011 MEV MB*MEV MB*MEV M093801500012 12.2 699.26 27.25 M093801500013 20.4 1594.52 45.77 M093801500014 28.5 1662.34 47.14 M093801500015 ENDDATA 5 0 M093801500016 ENDSUBENT 15 0 M093801599999 SUBENT M0938016 20170628 M090M093801600001 BIB 3 5 M093801600002 REACTION ((74-W-186(G,2N)74-W-184,,INT,,,EVAL)+ M093801600003 (74-W-186(G,2N+P)73-TA-183,,INT,,,EVAL)) M093801600004 ANALYSIS Integration of evaluated cross section. M093801600005 STATUS (DEP,M0938008) Evaluated cross section. M093801600006 Data from the Table 4. M093801600007 ENDBIB 5 0 M093801600008 NOCOMMON 0 0 M093801600009 DATA 3 2 M093801600010 EN-MAX DATA DATA-ERR M093801600011 MEV MB*MEV MB*MEV M093801600012 20.4 1012.53 37.20 M093801600013 28.5 1190.43 40.57 M093801600014 ENDDATA 4 0 M093801600015 ENDSUBENT 14 0 M093801699999 SUBENT M0938017 20170628 M090M093801700001 BIB 3 5 M093801700002 REACTION ((74-W-186(G,3N)74-W-183,,INT,,,EVAL)+ M093801700003 (74-W-186(G,3N+P)73-TA-182,,INT,,,EVAL)) M093801700004 ANALYSIS Integration of evaluated cross section. M093801700005 STATUS (DEP,M0938009) Evaluated cross section. M093801700006 Data from the Table 4. M093801700007 ENDBIB 5 0 M093801700008 NOCOMMON 0 0 M093801700009 DATA 3 1 M093801700010 EN-MAX DATA DATA-ERR M093801700011 MEV MB*MEV MB*MEV M093801700012 28.5 133.76 11.10 M093801700013 ENDDATA 3 0 M093801700014 ENDSUBENT 13 0 M093801799999 ENDENTRY 17 0 M093899999999