ENTRY M0968 20180411 M096M096800000001 SUBENT M0968001 20180411 M096M096800100001 BIB 9 31 M096800100002 TITLE The reliability of cross sections of partial M096800100003 photoneutron reactions for 98Mo. M096800100004 AUTHOR (V.V.Varlamov,V.D.Kaidarova,M.E.Stepanov) M096800100005 REFERENCE (J,VMU,1,68,2018) M096800100006 (J,MUPB,73,(1),68,2018) M096800100007 #DOI:10.3103/S0027134918010149 M096800100008 English translation M096800100009 of VMU,73,(1),68,2018. M096800100010 INSTITUTE (4RUSMOS) M096800100011 INC-SOURCE (QMPH,ARAD) M096800100012 ANALYSIS The joint analysis of data for total (g,xn) and M096800100013 partial (g,n), (g,2n) and (g,3n) reactions obtained M096800100014 in various experiments was carried out. The new M096800100015 approach to analysis of systematic disagreements M096800100016 between data was proposed on the base of new M096800100017 criteria of systematic uncertainties presence - M096800100018 specially proposed transitional multiplicity M096800100019 functions M096800100020 Fi-theor = SIG(g,in)/SIG(g,xn). M096800100021 Using these functions calculated in the frame of M096800100022 combined photonuclear reaction model new reliable M096800100023 and free from problems of neutron multiplicity M096800100024 sorting data for photoneutron partial reactions M096800100025 cross sections M096800100026 SIG-eval(g,in) = Fi-theor x SIG-exp(g,xn) M096800100027 were evaluated using experimental neutron yield M096800100028 reaction cross sections SIG-exp(g,xn). M096800100029 ERR-ANALYS (DATA-ERR) Root-mean-square errors. M096800100030 STATUS (APRVD) By V.Varlamov. M096800100031 HISTORY (20180411C) Data were compiled at the Russia MSU SINP M096800100032 CDFE by V.Varlamov. M096800100033 ENDBIB 31 0 M096800100034 NOCOMMON 0 0 M096800100035 ENDSUBENT 34 0 M096800199999 SUBENT M0968002 20180411 M096M096800200001 BIB 3 10 M096800200002 REACTION (42-MO-98(G,X)0-NN-1,UNW,SIG,,,EVAL) M096800200003 ANALYSIS The total neutron reaction cross section obtained as M096800200004 sum: SIG(g,sn) = SIG(g,n) + SIG(g,2n) + SIG(g,3n). M096800200005 STATUS (TABLE) Data plotted in Fig. 6. M096800200006 (DEP,M0968003) M096800200007 Evaluated (g,n) reaction cross section. M096800200008 (DEP,M0968004) M096800200009 Evaluated (g,2n) reaction cross section. M096800200010 (DEP,M0968004) M096800200011 Evaluated (g,3n) reaction cross section. M096800200012 ENDBIB 10 0 M096800200013 NOCOMMON 0 0 M096800200014 DATA 3 44 M096800200015 EN DATA DATA-ERR M096800200016 MEV MB MB M096800200017 8.96 14.21 1.42 M096800200018 9.36 16.88 1.69 M096800200019 9.76 19.97 2.00 M096800200020 10.16 23.78 2.38 M096800200021 10.56 28.41 2.85 M096800200022 10.96 33.87 3.40 M096800200023 11.36 40.56 4.07 M096800200024 11.96 53.94 5.41 M096800200025 12.16 59.60 5.98 M096800200026 12.56 72.68 7.29 M096800200027 12.96 88.43 8.87 M096800200028 13.36 107.06 10.73 M096800200029 13.76 125.59 12.59 M096800200030 14.16 144.12 14.45 M096800200031 14.56 158.53 15.90 M096800200032 14.96 167.79 16.82 M096800200033 15.36 175.00 17.55 M096800200034 15.76 184.57 18.51 M096800200035 16.16 210.82 21.14 M096800200036 16.56 229.97 23.06 M096800200037 16.96 236.76 23.74 M096800200038 17.36 236.76 23.74 M096800200039 17.76 229.25 22.99 M096800200040 18.16 215.76 21.63 M096800200041 18.56 199.09 19.96 M096800200042 18.96 181.17 18.17 M096800200043 19.36 164.09 16.45 M096800200044 19.96 141.03 14.14 M096800200045 20.16 134.24 13.46 M096800200046 20.56 122.00 12.23 M096800200047 20.96 111.97 11.23 M096800200048 21.36 103.51 10.38 M096800200049 21.76 96.24 9.65 M096800200050 22.16 92.70 9.29 M096800200051 22.56 86.57 8.68 M096800200052 22.96 81.10 8.13 M096800200053 23.36 75.81 7.60 M096800200054 23.76 71.28 7.15 M096800200055 24.16 66.96 6.71 M096800200056 24.56 63.36 6.35 M096800200057 24.96 60.72 6.09 M096800200058 25.56 58.25 5.84 M096800200059 26.16 57.90 5.81 M096800200060 26.76 58.50 5.87 M096800200061 ENDDATA 46 0 M096800200062 ENDSUBENT 61 0 M096800299999 SUBENT M0968003 20150813 M096M096800300001 BIB 4 21 M096800300002 REACTION ((42-MO-98(G,N)42-MO-97,,SIG,,,EVAL)+ M096800300003 (42-MO-98(G,N+P)41-NB-96,,SIG,,,EVAL)) M096800300004 ANALYSIS The contribution of partial reaction (g,n) cross M096800300005 section into the experimental total neutron yield M096800300006 reaction (g,xn) cross section obtained using M096800300007 quasimonoenergetic annihilation photons at Livermore M096800300008 (USA) was evaluated using specially theoretically M096800300009 calculated transitional multiplicity function - M096800300010 ratio M096800300011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M096800300012 by the way M096800300013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M096800300014 REL-REF (R,L0027011,A.Lepretre+,J,NP/A,175,609,1971)???????? M096800300015 Experimental data for the total neutron yield M096800300016 reaction (g,xn) cross section. M096800300017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M096800300018 Theoretical preequilibrium model of photonuclear M096800300019 reactions based on the Fermi gas densities. M096800300020 STATUS (TABLE) Data plotted in Fig. 6. M096800300021 (DEP,L0027011) M096800300022 The neutron yield reaction (g,xn) cross section. M096800300023 ENDBIB 21 0 M096800300024 NOCOMMON 0 0 M096800300025 DATA 3 43 M096800300026 EN DATA DATA-ERR M096800300027 MEV MB MB M096800300028 8.96 27.10 5.03 M096800300029 9.36 14.30 5.04 M096800300030 9.76 32.30 5.07 M096800300031 10.16 24.30 5.09 M096800300032 10.56 34.00 5.12 M096800300033 10.96 38.50 5.15 M096800300034 11.36 43.80 5.16 M096800300035 11.96 53.90 5.19 M096800300036 12.16 69.50 5.21 M096800300037 12.56 85.40 5.22 M096800300038 12.96 85.00 5.24 M096800300039 13.36 109.90 5.27 M096800300040 13.76 116.50 5.28 M096800300041 14.16 142.80 5.31 M096800300042 14.56 161.20 5.34 M096800300043 14.96 173.50 5.35 M096800300044 15.36 196.90 5.74 M096800300045 15.76 178.68 5.79 M096800300046 16.16 148.04 5.84 M096800300047 16.56 119.78 5.94 M096800300048 16.96 106.44 6.00 M096800300049 17.36 84.57 6.11 M096800300050 17.76 65.84 6.15 M096800300051 18.16 53.71 6.27 M096800300052 18.56 43.59 6.32 M096800300053 18.96 36.94 6.44 M096800300054 19.36 30.73 6.57 M096800300055 19.96 26.04 6.69 M096800300056 20.16 24.86 6.76 M096800300057 20.56 20.64 6.82 M096800300058 20.96 21.38 6.90 M096800300059 21.36 21.07 7.03 M096800300060 21.76 19.64 7.09 M096800300061 22.16 13.03 7.23 M096800300062 22.56 15.63 7.31 M096800300063 22.96 17.01 7.44 M096800300064 23.36 13.51 7.51 M096800300065 23.76 12.36 7.66 M096800300066 24.16 11.47 7.73 M096800300067 24.56 9.87 7.80 M096800300068 24.96 9.38 8.91 M096800300069 25.56 8.07 9.05 M096800300070 26.16 7.89 9.20 M096800300071 ENDDATA 45 0 M096800300072 ENDSUBENT 71 0 M096800399999 SUBENT M0968004 20050221 M096M096800400001 BIB 4 20 M096800400002 REACTION (42-MO-98(G,2N)42-MO-96,,SIG,,,EVAL) M096800400003 ANALYSIS The contribution of partial reaction (g,2n) cross M096800400004 section into the experimental total neutron yield M096800400005 reaction (g,xn) cross section obtained using M096800400006 quasimonoenergetic annihilation photons at Livermore M096800400007 (USA) was evaluated using specially theoretically M096800400008 calculated transitional multiplicity function - M096800400009 ratio M096800400010 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M096800400011 by the way M096800400012 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M096800400013 REL-REF (R,L0027011,A.Lepretre+,J,NP/A,175,609,1971) M096800400014 Experimental data for the total neutron yield M096800400015 reaction (g,xn) cross section. M096800400016 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M096800400017 Theoretical preequilibrium model of photonuclear M096800400018 reactions based on the Fermi gas densities. M096800400019 STATUS (TABLE) Data plotted in Fig. 6. M096800400020 (DEP,L0027011) M096800400021 The neutron yield reaction (g,xn) cross section. M096800400022 ENDBIB 20 0 M096800400023 NOCOMMON 0 0 M096800400024 DATA 3 27 M096800400025 EN DATA DATA-ERR M096800400026 MEV MB MB M096800400027 15.76 6.01 5.79 M096800400028 16.16 30.53 5.84 M096800400029 16.56 48.01 5.94 M096800400030 16.96 64.48 6.01 M096800400031 17.36 71.07 6.12 M096800400032 17.76 73.18 6.16 M096800400033 18.16 75.49 6.28 M096800400034 18.56 74.01 6.33 M096800400035 18.96 72.33 6.45 M096800400036 19.36 66.83 6.58 M096800400037 19.96 61.93 6.70 M096800400038 20.16 59.92 6.77 M096800400039 20.56 50.52 6.83 M096800400040 20.96 52.12 6.91 M096800400041 21.36 51.26 7.04 M096800400042 21.76 47.85 7.10 M096800400043 22.16 33.58 7.24 M096800400044 22.56 42.46 7.32 M096800400045 22.96 49.33 7.45 M096800400046 23.36 42.22 7.52 M096800400047 23.76 41.43 7.67 M096800400048 24.16 40.38 7.74 M096800400049 24.56 36.00 7.81 M096800400050 24.96 35.15 8.92 M096800400051 25.56 30.08 9.06 M096800400052 26.16 27.62 9.21 M096800400053 26.76 15.91 9.43 M096800400054 ENDDATA 29 0 M096800400055 ENDSUBENT 54 0 M096800499999 SUBENT M0968005 20050221 M096M096800500001 BIB 4 20 M096800500002 REACTION (42-MO-98(G,3N)42-MO-95,,SIG,,,EVAL) M096800500003 ANALYSIS The contribution of partial reaction (g,3n) cross M096800500004 section into the experimental total neutron yield M096800500005 reaction (g,xn) cross section obtained using M096800500006 quasimonoenergetic annihilation photons at Livermore M096800500007 (USA) was evaluated using specially theoretically M096800500008 calculated transitional multiplicity function - M096800500009 ratio M096800500010 F3-theor = SIG-theor(g,3n)/SIG-theor(g,xn) M096800500011 by the way M096800500012 SIG-eval(g,3n) = (F2-theor)x(SIG-exp(g,xn)). M096800500013 REL-REF (R,L0027011,A.Lepretre+,J,NP/A,175,609,1971) M096800500014 Experimental data for the total neutron yield M096800500015 reaction (g,xn) cross section. M096800500016 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M096800500017 Theoretical preequilibrium model of photonuclear M096800500018 reactions based on the Fermi gas densities. M096800500019 STATUS (TABLE) Data plotted in Fig. 6. M096800500020 (DEP,L0027011) M096800500021 The neutron yield reaction (g,xn) cross section. M096800500022 ENDBIB 20 0 M096800500023 NOCOMMON 0 0 M096800500024 DATA 3 3 M096800500025 EN DATA DATA-ERR M096800500026 MEV MB MB M096800500027 25.56 0.72 0.11 M096800500028 26.16 2.79 0.44 M096800500029 26.76 3.57 0.77 M096800500030 ENDDATA 5 0 M096800500031 ENDSUBENT 30 0 M096800599999 ENDENTRY 5 0 M096899999999