ENTRY M0976 20190131 M099M097600000001 SUBENT M0976001 20190131 M099M097600100001 BIB 9 28 M097600100002 TITLE Photoneutron reaction cross-section data for 75As: M097600100003 experiments and evaluation. M097600100004 AUTHOR (V.Varlamov,A.Davydov,V.Kaidarova,V.Orlin) M097600100005 REFERENCE (J,PR/C,99,024608,2019) M097600100006 #doi:10.1103/PhysRevC.99.024608 M097600100007 INSTITUTE (4RUSMOS) M097600100008 INC-SOURCE (QMPH,ARAD) M097600100009 ANALYSIS The joint analysis of data for total (g,xn) and M097600100010 partial (g,n) and (g,2n) reactions obtained in M097600100011 various experiments was carried out. The new M097600100012 approach to analysis of systematic disagreements M097600100013 between data was proposed on the base of new M097600100014 criteria of systematic uncertainties presence - M097600100015 specially proposed transitional multiplicity M097600100016 functions M097600100017 Fi-theor = SIG(g,in)/SIG(g,xn). M097600100018 Using these functions calculated in the frame of M097600100019 combined photonuclear reaction model new reliable M097600100020 and free from problems of neutron multiplicity M097600100021 sorting data for photoneutron partial reactions M097600100022 cross sections M097600100023 SIG-eval(g,in) = Fi-theor x SIG-exp(g,xn) M097600100024 were evaluated using experimental neutron yield M097600100025 reaction cross sections SIG-exp(g,xn). M097600100026 ERR-ANALYS (DATA-ERR) Root-mean-squared errors. M097600100027 STATUS (APRVD) By V.Varlamov. M097600100028 HISTORY (20190131C) Data were compiled at the Russia MSU SINP M097600100029 CDFE by V.Varlamov. M097600100030 ENDBIB 28 0 M097600100031 NOCOMMON 0 0 M097600100032 ENDSUBENT 31 0 M097600199999 SUBENT M0976002 20190131 M099M097600200001 BIB 3 8 M097600200002 REACTION (33-AS-75(G,X)0-NN-1,UNW,SIG,,,EVAL) M097600200003 ANALYSIS The total neutron reaction cross section obtained as M097600200004 sum: SIG(g,sn) = SIG(g,n) + SIG(g,2n). M097600200005 STATUS (TABLE) Data plotted in Fig. 3. M097600200006 (DEP,M0976003) M097600200007 Evaluated (g,n) reaction cross section. M097600200008 (DEP,M0976004) M097600200009 Evaluated (g,2n) reaction cross section. M097600200010 ENDBIB 8 0 M097600200011 NOCOMMON 0 0 M097600200012 DATA 3 58 M097600200013 EN DATA DATA-ERR M097600200014 MEV MB MB M097600200015 10.74 14.80 4.12 M097600200016 11.01 19.10 4.44 M097600200017 11.28 22.40 4.70 M097600200018 11.55 23.70 4.81 M097600200019 11.82 29.10 5.22 M097600200020 12.09 34.80 5.64 M097600200021 12.36 37.90 5.88 M097600200022 12.63 41.80 6.18 M097600200023 12.91 46.80 6.56 M097600200024 13.18 51.80 6.93 M097600200025 13.45 65.30 7.90 M097600200026 13.72 72.30 8.41 M097600200027 13.99 84.60 9.30 M097600200028 14.26 89.90 9.69 M097600200029 14.53 100.80 10.49 M097600200030 14.80 104.20 10.74 M097600200031 15.07 105.30 10.85 M097600200032 15.34 113.20 11.42 M097600200033 15.62 113.90 11.50 M097600200034 15.89 116.20 11.68 M097600200035 16.16 119.90 11.97 M097600200036 16.43 118.30 11.88 M097600200037 16.70 110.60 11.37 M097600200038 16.97 111.50 11.46 M097600200039 17.24 110.00 11.38 M097600200040 17.51 112.30 11.56 M097600200041 17.78 107.00 11.98 M097600200042 18.05 104.60 11.86 M097600200043 18.33 97.39 11.27 M097600200044 18.60 98.52 10.94 M097600200045 18.87 95.14 9.91 M097600200046 19.14 94.16 9.08 M097600200047 19.41 90.85 8.16 M097600200048 19.68 78.37 6.91 M097600200049 19.95 76.30 6.39 M097600200050 20.22 72.22 6.00 M097600200051 20.49 69.56 5.77 M097600200052 20.76 68.25 5.69 M097600200053 21.04 58.75 5.21 M097600200054 21.31 65.90 5.58 M097600200055 21.58 65.66 5.56 M097600200056 21.85 60.95 5.35 M097600200057 22.12 63.95 5.55 M097600200058 22.39 62.18 5.48 M097600200059 22.66 59.28 5.36 M097600200060 22.93 54.18 5.13 M097600200061 23.20 56.83 5.28 M097600200062 23.47 47.19 4.81 M097600200063 23.75 46.46 4.83 M097600200064 24.02 46.59 4.85 M097600200065 24.29 43.28 4.68 M097600200066 24.56 47.19 4.91 M097600200067 24.83 40.26 4.59 M097600200068 25.10 43.91 4.80 M097600200069 25.37 36.98 4.48 M097600200070 25.64 36.41 4.47 M097600200071 25.91 34.65 4.40 M097600200072 26.18 27.53 4.07 M097600200073 ENDDATA 60 0 M097600200074 ENDSUBENT 73 0 M097600299999 SUBENT M0976003 20190131 M099M097600300001 BIB 4 20 M097600300002 REACTION ((33-AS-75(G,N)33-AS-74,,SIG,,,EVAL)+ M097600300003 (33-AS-75(G,N+P)32-GE-73,,SIG,,,EVAL)) M097600300004 ANALYSIS The contribution of partial reaction (g,n) cross M097600300005 section into the experimental total neutron yield M097600300006 reaction (g,xn) cross section obtained using M097600300007 quasimonoenergetic annihilation photons at Saclay M097600300008 (France) was evaluated using specially theoretically M097600300009 calculated transitional multiplicity function ratio M097600300010 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M097600300011 by the way M097600300012 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M097600300013 REL-REF (R,L0043022,P.Carlos+,J,NP/A,258,365,1976) M097600300014 Experimental data for the total neutron yield M097600300015 reaction (g,xn) cross section. M097600300016 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097600300017 Theoretical preequilibrium model of photonuclear M097600300018 reactions based on the Fermi gas densities. M097600300019 STATUS (TABLE) Data plotted in Fig. 3. M097600300020 (DEP,L0043022) M097600300021 The neutron yield reaction (g,xn) cross section. M097600300022 ENDBIB 20 0 M097600300023 NOCOMMON 0 0 M097600300024 DATA 3 58 M097600300025 EN DATA DATA-ERR M097600300026 MEV MB MB M097600300027 10.74 14.80 4.12 M097600300028 11.01 19.10 4.44 M097600300029 11.28 22.40 4.70 M097600300030 11.55 23.70 4.81 M097600300031 11.82 29.10 5.22 M097600300032 12.09 34.80 5.64 M097600300033 12.36 37.90 5.88 M097600300034 12.63 41.80 6.18 M097600300035 12.91 46.80 6.56 M097600300036 13.18 51.80 6.93 M097600300037 13.45 65.30 7.90 M097600300038 13.72 72.30 8.41 M097600300039 13.99 84.60 9.30 M097600300040 14.26 89.90 9.69 M097600300041 14.53 100.80 10.49 M097600300042 14.80 104.20 10.74 M097600300043 15.07 105.30 10.85 M097600300044 15.34 113.20 11.42 M097600300045 15.62 113.90 11.50 M097600300046 15.89 116.20 11.68 M097600300047 16.16 119.90 11.97 M097600300048 16.43 118.30 11.88 M097600300049 16.70 110.60 11.37 M097600300050 16.97 111.50 11.46 M097600300051 17.24 110.00 11.38 M097600300052 17.51 112.30 11.56 M097600300053 17.78 107.00 11.98 M097600300054 18.05 104.60 11.86 M097600300055 18.33 97.39 11.27 M097600300056 18.60 95.40 10.94 M097600300057 18.87 86.59 9.86 M097600300058 19.14 79.59 8.93 M097600300059 19.41 70.15 7.83 M097600300060 19.68 55.07 6.36 M097600300061 19.95 47.96 5.50 M097600300062 20.22 41.42 4.82 M097600300063 20.49 36.89 4.32 M097600300064 20.76 33.60 3.96 M097600300065 21.04 27.54 3.45 M097600300066 21.31 29.29 3.48 M097600300067 21.58 28.59 3.40 M097600300068 21.85 26.54 3.27 M097600300069 22.12 28.42 3.47 M097600300070 22.39 27.64 3.42 M097600300071 22.66 26.35 3.35 M097600300072 22.93 24.08 3.20 M097600300073 23.20 25.26 3.30 M097600300074 23.47 21.72 3.12 M097600300075 23.75 21.78 3.20 M097600300076 24.02 21.84 3.21 M097600300077 24.29 19.92 3.04 M097600300078 24.56 20.97 3.07 M097600300079 24.83 17.89 2.87 M097600300080 25.10 19.52 3.00 M097600300081 25.37 16.44 2.80 M097600300082 25.64 16.18 2.79 M097600300083 25.91 15.40 2.75 M097600300084 26.18 12.24 2.54 M097600300085 ENDDATA 60 0 M097600300086 ENDSUBENT 85 0 M097600399999 SUBENT M0976004 20190131 M099M097600400001 BIB 4 19 M097600400002 REACTION (64-GD-160(G,2N)64-GD-158,,SIG,,,EVAL) M097600400003 ANALYSIS The contribution of partial reaction (g,2n) cross M097600400004 section into the experimental total neutron yield M097600400005 reaction (g,xn) cross section obtained using M097600400006 quasimonoenergetic annihilation photons at Saclay M097600400007 (France) was evaluated using specially theoretically M097600400008 calculated transitional multiplicity function ratio M097600400009 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M097600400010 by the way M097600400011 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M097600400012 REL-REF (R,L0043022,P.Carlos+,J,NP/A,258,365,1976) M097600400013 Experimental data for the total neutron yield M097600400014 reaction (g,xn) cross section. M097600400015 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097600400016 Theoretical preequilibrium model of photonuclear M097600400017 reactions based on the Fermi gas densities. M097600400018 STATUS (TABLE) Data plotted in Fig. 3. M097600400019 (DEP,L0043022) M097600400020 The neutron yield reaction (g,xn) cross section. M097600400021 ENDBIB 19 0 M097600400022 NOCOMMON 0 0 M097600400023 DATA 3 29 M097600400024 EN DATA DATA-ERR M097600400025 MEV MB MB M097600400026 18.60 3.11 0.36 M097600400027 18.87 8.55 0.97 M097600400028 19.14 14.57 1.64 M097600400029 19.41 20.70 2.31 M097600400030 19.68 23.30 2.69 M097600400031 19.95 28.34 3.25 M097600400032 20.22 30.80 3.58 M097600400033 20.49 32.67 3.83 M097600400034 20.76 34.65 4.08 M097600400035 21.04 31.21 3.91 M097600400036 21.31 36.61 4.35 M097600400037 21.58 37.07 4.40 M097600400038 21.85 34.41 4.24 M097600400039 22.12 35.53 4.33 M097600400040 22.39 34.55 4.28 M097600400041 22.66 32.94 4.18 M097600400042 22.93 30.10 4.00 M097600400043 23.20 31.57 4.12 M097600400044 23.47 25.47 3.66 M097600400045 23.75 24.68 3.62 M097600400046 24.02 24.75 3.64 M097600400047 24.29 23.36 3.56 M097600400048 24.56 26.22 3.84 M097600400049 24.83 22.37 3.59 M097600400050 25.10 24.40 3.74 M097600400051 25.37 20.55 3.50 M097600400052 25.64 20.23 3.49 M097600400053 25.91 19.25 3.44 M097600400054 26.18 15.30 3.18 M097600400055 ENDDATA 31 0 M097600400056 ENDSUBENT 55 0 M097600499999 SUBENT M0976005 20190131 M099M097600500001 BIB 3 4 M097600500002 REACTION (33-AS-75(G,X)0-NN-1,UNW,INT,,,EVAL) M097600500003 ANALYSIS Integration of evaluated cross section. M097600500004 STATUS (DEP,M0976002) Evaluated cross section. M097600500005 (TABLE) Data from Table 2. M097600500006 ENDBIB 4 0 M097600500007 NOCOMMON 0 0 M097600500008 DATA 3 29 M097600500009 EN-MAX DATA DATA-ERR M097600500010 MEV MB*MEV MB*MEV M097600500011 18.2 596.80 9.47 M097600500012 26.2 1090.40 11.57 M097600500013 ENDDATA 4 0 M097600500014 ENDSUBENT 13 0 M097600599999 SUBENT M0976006 20190131 M099M097600600001 BIB 3 5 M097600600002 REACTION ((33-AS-75(G,N)33-AS-74,,INT,,,EVAL)+ M097600600003 (33-AS-75(G,N+P)32-GE-73,,INT,,,EVAL)) M097600600004 ANALYSIS Integration of evaluated cross section. M097600600005 STATUS (DEP,M0976003) Evaluated cross section. M097600600006 (TABLE) Data from Table 2. M097600600007 ENDBIB 5 0 M097600600008 NOCOMMON 0 0 M097600600009 DATA 3 29 M097600600010 EN-MAX DATA DATA-ERR M097600600011 MEV MB*MEV MB*MEV M097600600012 18.2 596.80 9.47 M097600600013 26.2 890.14 10.98 M097600600014 ENDDATA 4 0 M097600600015 ENDSUBENT 14 0 M097600699999 SUBENT M0976007 20190131 M099M097600700001 BIB 3 4 M097600700002 REACTION (33-AS-75(G,2N)33-AS-73,,INT,,,EVAL) M097600700003 ANALYSIS Integration of evaluated cross section. M097600700004 STATUS (DEP,M0976004) Evaluated cross section. M097600700005 (TABLE) Data from Table 2. M097600700006 ENDBIB 4 0 M097600700007 NOCOMMON 0 0 M097600700008 DATA 3 19 M097600700009 EN-MAX DATA DATA-ERR M097600700010 MEV MB*MEV MB*MEV M097600700011 26.2 200.27 3.66 M097600700012 ENDDATA 3 0 M097600700013 ENDSUBENT 12 0 M097600799999 ENDENTRY 7 0 M097699999999