ENTRY M0977 20190611 M100M097700000001 SUBENT M0977001 20190611 M100M097700100001 BIB 9 35 M097700100002 TITLE Evaluation of reliable cross sections of photoneutron M097700100003 reactions on 103Rh and 165Ho nuclei. M097700100004 AUTHOR (V.V.Varlamov,A.I.Davydov,V.D.Kaidarova) M097700100005 REFERENCE (J,YF,82,196,2019) M097700100006 #doi:10.1134/S0044002719030152 M097700100007 (J,PAN,82,212,2019) M097700100008 English translation of YF,82,196,2019. M097700100009 #doi:10.1134/S1063778819030153 M097700100010 (C,2018VORNZH,,97,2018) M097700100011 New photoneutron reaction cross section data for M097700100012 153Eu and 165Ho. M097700100013 Data for 165Ho. M097700100014 INSTITUTE (4RUSMOS) M097700100015 INC-SOURCE (QMPH,ARAD) M097700100016 ANALYSIS The joint analysis of data for total (gamma,xn) and M097700100017 partial (gamma,n),(gamma,2n) and (gamma,3n) M097700100018 reactions obtained in various experiments was M097700100019 carried out. The new approach to analysis of M097700100020 systematic disagreements between data was proposed M097700100021 on the base of new criteria of systematic M097700100022 uncertainties presence - specially proposed M097700100023 transitional multiplicity functions M097700100024 Fi-theor = SIG(gamma,in)/SIG(gamma,xn). M097700100025 Using these functions calculated in the frame of M097700100026 combined photonuclear reaction model new reliable M097700100027 and free from problems of neutron multiplicity M097700100028 sorting data for photoneutron partial reactions M097700100029 cross sections M097700100030 SIG-eval(gamma,in) = Fi-theor x SIG-exp(gamma,xn) M097700100031 were evaluated using experimental neutron yield M097700100032 reaction cross sections SIG-exp(gamma,xn). M097700100033 ERR-ANALYS (DATA-ERR) Mean-root-squared errors. M097700100034 STATUS (APRVD) Approved by V.Varlamov. M097700100035 HISTORY (20190611C) Data were compiled at the Russia MSU SINP M097700100036 CDFE by V.Varlamov. M097700100037 ENDBIB 35 0 M097700100038 NOCOMMON 0 0 M097700100039 ENDSUBENT 38 0 M097700199999 SUBENT M0977002 20190611 M100M097700200001 BIB 3 9 M097700200002 REACTION (45-RH-103(G,X)0-NN-1,UNW,SIG,,,EVAL) M097700200003 ANALYSIS The total neutron reaction cross section obtained as M097700200004 sum: SIG(gamma,sn) = SIG(gamma,1n) + SIG(gamma,2n). M097700200005 STATUS (DEP,M0977003) M097700200006 Evaluated (gamma,1n) reaction cross section. M097700200007 (DEP,M0977004) M097700200008 Evaluated (gamma,2n) reaction cross section. M097700200009 (TABLE) Data presented in Fig. 6 of M097700200010 Yad.Fiz.,82(2019)196. M097700200011 ENDBIB 9 0 M097700200012 NOCOMMON 0 0 M097700200013 DATA 3 58 M097700200014 EN DATA DATA-ERR M097700200015 MEV MB MB M097700200016 9.2 0.00 0.34 M097700200017 9.4 0.08 0.93 M097700200018 9.7 2.45 1.98 M097700200019 10.0 14.91 5.70 M097700200020 10.2 24.22 7.28 M097700200021 10.5 26.99 8.26 M097700200022 10.8 31.90 9.06 M097700200023 11.1 36.60 9.57 M097700200024 11.3 41.90 11.29 M097700200025 11.6 50.00 13.22 M097700200026 11.9 56.10 14.76 M097700200027 12.2 66.30 15.70 M097700200028 12.4 73.40 16.08 M097700200029 12.7 83.00 16.66 M097700200030 12.9 89.40 20.80 M097700200031 13.2 98.50 22.28 M097700200032 13.5 114.50 23.83 M097700200033 13.8 129.70 28.70 M097700200034 14.0 133.90 29.39 M097700200035 14.3 152.60 30.72 M097700200036 14.6 159.50 34.41 M097700200037 14.8 170.30 36.76 M097700200038 15.1 170.10 34.00 M097700200039 15.4 181.70 38.58 M097700200040 15.6 190.00 40.96 M097700200041 15.9 187.90 37.52 M097700200042 16.2 187.30 39.23 M097700200043 16.5 186.40 40.74 M097700200044 16.7 192.00 39.03 M097700200045 17.0 184.30 39.00 M097700200046 17.3 179.70 40.50 M097700200047 17.5 176.20 37.35 M097700200048 17.8 170.90 38.41 M097700200049 18.1 156.90 38.57 M097700200050 18.4 142.10 33.61 M097700200051 18.6 131.40 32.22 M097700200052 18.9 127.40 34.32 M097700200053 19.2 119.40 30.94 M097700200054 19.4 114.40 29.77 M097700200055 19.7 109.80 34.74 M097700200056 19.8 103.00 33.44 M097700200057 20.0 96.09 24.56 M097700200058 20.3 91.77 24.88 M097700200059 20.6 81.20 20.59 M097700200060 20.9 82.44 24.07 M097700200061 21.1 79.87 21.98 M097700200062 21.4 75.12 21.49 M097700200063 21.7 76.79 22.96 M097700200064 21.9 71.42 20.16 M097700200065 22.2 68.09 19.51 M097700200066 22.5 64.72 19.96 M097700200067 22.8 62.28 18.25 M097700200068 23.0 53.27 16.04 M097700200069 23.6 51.01 15.97 M097700200070 24.1 48.87 16.20 M097700200071 24.7 44.24 14.01 M097700200072 25.2 39.57 14.20 M097700200073 25.8 41.46 16.53 M097700200074 ENDDATA 60 0 M097700200075 ENDSUBENT 74 0 M097700299999 SUBENT M0977003 20190611 M100M097700300001 BIB 4 24 M097700300002 REACTION ((45-RH-103(G,N)45-RH-102,,SIG,,,EVAL)+ M097700300003 (45-RH-103(G,N+P)44-RU-101,,SIG,,,EVAL)) M097700300004 ANALYSIS The contribution of partial reaction (gamma,n) cross M097700300005 section into the experimental total neutron yield M097700300006 reaction (gamma,xn) cross section obtained using M097700300007 quasimonoenergetic annihilation photons at Saclay M097700300008 was evaluated using specially theoretically M097700300009 calculated transitional multiplicity function - M097700300010 ratio M097700300011 F1-theor = SIG-theor(gamma,n)/SIG-theor(gamma,xn) M097700300012 by the way M097700300013 SIG-eval(gamma,n) = (F1-theor)x(SIG-exp(gamma,xn)). M097700300014 The neutron yield cross section was obtained at M097700300015 Saclay. M097700300016 REL-REF (R,L0035002,A.Lepretre+,J,NP/A,219,39,1974) M097700300017 Experimental data for the total neutron yield M097700300018 reaction (gamma,xn) cross section. M097700300019 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097700300020 Theoretical preequilibrium model of photonuclear M097700300021 reactions based on the Fermi gas densities. M097700300022 STATUS (DEP,L0035002) M097700300023 The neutron yield reaction (gamma,xn) cross section. M097700300024 (TABLE) Data presented in Fig. 6 of M097700300025 Yad.Fiz.,82(2019)196. M097700300026 ENDBIB 24 0 M097700300027 NOCOMMON 0 0 M097700300028 DATA 3 58 M097700300029 EN DATA DATA-ERR M097700300030 MEV MB MB M097700300031 9.2 0.00 0.27 M097700300032 9.4 0.08 0.75 M097700300033 9.7 2.45 1.69 M097700300034 10.0 14.91 5.34 M097700300035 10.2 24.22 6.88 M097700300036 10.5 26.99 7.78 M097700300037 10.8 31.90 8.51 M097700300038 11.1 36.60 8.98 M097700300039 11.3 41.90 10.55 M097700300040 11.6 50.00 12.31 M097700300041 11.9 56.10 13.72 M097700300042 12.2 66.30 14.58 M097700300043 12.4 73.40 14.92 M097700300044 12.7 83.00 15.46 M097700300045 12.9 89.40 19.23 M097700300046 13.2 98.50 20.58 M097700300047 13.5 114.50 21.99 M097700300048 13.8 129.70 26.42 M097700300049 14.0 133.90 27.06 M097700300050 14.3 152.60 28.27 M097700300051 14.6 159.50 31.64 M097700300052 14.8 170.30 33.78 M097700300053 15.1 170.10 31.27 M097700300054 15.4 181.70 35.44 M097700300055 15.6 190.00 37.61 M097700300056 15.9 187.90 34.49 M097700300057 16.2 187.30 36.05 M097700300058 16.5 186.40 37.43 M097700300059 16.7 192.00 35.92 M097700300060 17.0 184.20 35.90 M097700300061 17.3 177.60 37.14 M097700300062 17.5 162.70 32.34 M097700300063 17.8 142.70 31.68 M097700300064 18.1 114.60 29.26 M097700300065 18.4 90.79 23.85 M097700300066 18.6 73.52 21.86 M097700300067 18.9 62.46 22.12 M097700300068 19.2 51.77 19.04 M097700300069 19.4 44.67 17.85 M097700300070 19.7 39.56 20.43 M097700300071 19.8 36.74 19.61 M097700300072 20.0 31.90 13.91 M097700300073 20.3 29.57 14.02 M097700300074 20.6 26.29 11.44 M097700300075 20.9 27.41 13.61 M097700300076 21.1 27.83 12.50 M097700300077 21.4 27.58 12.34 M097700300078 21.7 29.83 13.49 M097700300079 21.9 28.83 11.87 M097700300080 22.2 28.06 11.52 M097700300081 22.5 26.83 11.82 M097700300082 22.8 25.56 10.68 M097700300083 23.0 21.43 9.22 M097700300084 23.6 19.42 8.99 M097700300085 24.1 17.54 8.96 M097700300086 24.7 14.98 7.47 M097700300087 25.2 12.75 7.45 M097700300088 25.8 12.71 8.73 M097700300089 ENDDATA 60 0 M097700300090 ENDSUBENT 89 0 M097700399999 SUBENT M0977004 20190611 M100M097700400001 BIB 4 23 M097700400002 REACTION (45-RH-103(G,2N)45-RH-101,,SIG,,,EVAL) M097700400003 ANALYSIS The contribution of partial reaction (gamma,2n) cross M097700400004 section into the experimental total neutron yield M097700400005 reaction (gamma,xn) cross section obtained using M097700400006 quasimonoenergetic annihilation photons at Saclay M097700400007 was evaluated using specially theoretically M097700400008 calculated transitional multiplicity function - M097700400009 ratio M097700400010 F2-theor = SIG-theor(gamma,2n)/SIG-theor(gamma,xn) M097700400011 by the way M097700400012 SIG-eval(gamma,2n) = (F2-theor)x(SIG-exp(gamma,xn)). M097700400013 The neutron yield cross section was obtained at M097700400014 Saclay. M097700400015 REL-REF (R,L0035002,A.Lepretre+,J,NP/A,219,39,1974) M097700400016 Experimental data for the total neutron yield M097700400017 reaction (gamma,xn) cross section. M097700400018 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097700400019 Theoretical preequilibrium model of photonuclear M097700400020 reactions based on the Fermi gas densities. M097700400021 STATUS (DEP,L0035002) M097700400022 The neutron yield reaction (gamma,xn) cross section. M097700400023 (TABLE) Data presented in Fig. 6 of M097700400024 Yad.Fiz.,82(2019)196. M097700400025 ENDBIB 23 0 M097700400026 NOCOMMON 0 0 M097700400027 DATA 3 30 M097700400028 EN DATA DATA-ERR M097700400029 MEV MB MB M097700400030 16.7 0.00 2.98 M097700400031 17.0 0.08 2.98 M097700400032 17.3 2.14 3.22 M097700400033 17.5 13.47 4.88 M097700400034 17.8 28.23 6.59 M097700400035 18.1 42.37 9.16 M097700400036 18.4 51.30 9.62 M097700400037 18.6 57.89 10.22 M097700400038 18.9 64.95 12.06 M097700400039 19.2 67.64 11.77 M097700400040 19.4 69.69 11.79 M097700400041 19.7 70.25 14.15 M097700400042 19.8 66.30 13.68 M097700400043 20.0 64.18 10.54 M097700400044 20.3 62.20 10.76 M097700400045 20.6 54.91 9.07 M097700400046 20.9 55.03 10.36 M097700400047 21.1 52.04 9.39 M097700400048 21.4 47.53 9.06 M097700400049 21.7 46.95 9.38 M097700400050 21.9 42.60 8.21 M097700400051 22.2 40.03 7.92 M097700400052 22.5 37.89 8.06 M097700400053 22.8 36.73 7.50 M097700400054 23.0 31.84 6.76 M097700400055 23.6 31.60 6.92 M097700400056 24.1 31.33 7.17 M097700400057 24.7 29.26 6.49 M097700400058 25.2 26.82 6.69 M097700400059 25.8 28.75 7.74 M097700400060 ENDDATA 32 0 M097700400061 ENDSUBENT 60 0 M097700499999 SUBENT M0977005 20190528 M100M097700500001 BIB 3 4 M097700500002 REACTION (45-RH-103(G,X)0-NN-1,UNW,INT,,,EVAL) M097700500003 ANALYSIS Integration of evaluated cross section. M097700500004 STATUS (TABLE) Table 1 from Yad.Fiz.,82(2019)196 M097700500005 (DEP,M0977002) Evaluated cross section. M097700500006 ENDBIB 4 0 M097700500007 NOCOMMON 0 0 M097700500008 DATA 3 49 M097700500009 EN-MAX DATA DATA-ERR M097700500010 MEV MB*MEV MB*MEV M097700500011 16.7 747.4 39.0 M097700500012 21.0 1391.4 55.6 M097700500013 24.0 1507.8 57.9 M097700500014 26.0 1594.4 60.2 M097700500015 ENDDATA 6 0 M097700500016 ENDSUBENT 15 0 M097700599999 SUBENT M0977006 20190528 M100M097700600001 BIB 3 5 M097700600002 REACTION ((45-RH-103(G,N)45-RH-102,,INT,,,EVAL)+ M097700600003 (45-RH-103(G,N+P)44-RU-101,,INT,,,EVAL)) M097700600004 ANALYSIS Integration of evaluated cross section. M097700600005 STATUS (TABLE) Table 1 from Yad.Fiz.,82(2019)196. M097700600006 (DEP,M0977003) Evaluated cross section. M097700600007 ENDBIB 5 0 M097700600008 NOCOMMON 0 0 M097700600009 DATA 3 49 M097700600010 EN-MAX DATA DATA-ERR M097700600011 MEV MB*MEV MB*MEV M097700600012 16.7 747.4 36.0 M097700600013 21.0 1157.5 46.6 M097700600014 24.0 1204.1 47.5 M097700600015 26.0 1233.1 48.3 M097700600016 ENDDATA 6 0 M097700600017 ENDSUBENT 16 0 M097700699999 SUBENT M0977007 20190528 M100M097700700001 BIB 3 4 M097700700002 REACTION (45-RH-103(G,2N)45-RH-101,,INT,,,EVAL) M097700700003 ANALYSIS Integration of evaluated cross section. M097700700004 STATUS (TABLE) Table 1 from Yad.Fiz.,82(2019)196. M097700700005 (DEP,M0977004) Evaluated cross section. M097700700006 ENDBIB 4 0 M097700700007 NOCOMMON 0 0 M097700700008 DATA 3 39 M097700700009 EN-MAX DATA DATA-ERR M097700700010 MEV MB*MEV MB*MEV M097700700011 21.0 234.0 12.0 M097700700012 24.0 303.8 13.8 M097700700013 26.0 361.3 15.9 M097700700014 ENDDATA 5 0 M097700700015 ENDSUBENT 14 0 M097700799999 ENDENTRY 7 0 M097799999999