IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 7.71930+ 4 1.91305+ 2 1 0 0 27793 1451 1 0.00000+ 0 0.00000+ 0 0 0 0 67793 1451 2 1.00000+ 0 2.00000+ 7 0 0 10 937793 1451 3 0.00000+ 0 0.00000+ 0 0 0 156 277793 1451 4 77-Ir-193 FEI EVAL-JAN90 NIKOLAEV M.N. 7793 1451 5 REF.SEE MT=451 DIST- REV1-JAN93 1801937793 1451 6 ----FOND-2 MATERIAL 7793 7793 1451 7 -----INCIDENT NEUTRON ACTIVATION DATA 7793 1451 8 ------ENDF-6 FORMAT 7793 1451 9 7793 1451 10 ***************************************************************** 7793 1451 11 7793 1451 12 RESULTS OF EVALUATION FULFILLED BY NIKOLAEV M.N. ARE GIVEN. 7793 1451 13 DATA COMPILED AND CHECKED BY G.V.SAVOSKINA. 7793 1451 14 7793 1451 15 COMMENTS TO CONTENT: 7793 1451 16 MF=1 7793 1451 17 MT=451. DESCRIPTION IS WRITTED DOWN BY NIKOLAEV M.N. 7793 1451 18 MF=2 - RESONANCE REGION. 7793 1451 19 ----------------- 7793 1451 20 MT=151. RESOLVED RESONANCE REGION EXTENTS FOR IR-193 FROM 7793 1451 21 1.0-5 EV TO 300 EV (BOUND LEVEL +39 S-RESONANCES +5 7793 1451 22 ARTIFICAL S-RESONANCES OUT OF REGION). RESONANCE PA- 7793 1451 23 RAMETERS ARE TAKEN FROM /1/. ARTIFICAL RESONANCES 7793 1451 24 USED FOR TAKING INTO ACCOUNT UNRESOLVED RESONANCES 7793 1451 25 CONTRIBUTIONS. THEIR ENERGIES ARE TAKEN FROM /1/. 7793 1451 26 AVERAGE WIDTHS ARE ADOPTED FOR ARTIFICAL RESONANCES. 7793 1451 27 MF=3 - CROSS-SECTIONS. 7793 1451 28 -------------- 7793 1451 29 IN THE REGION 0.00001 -300 EV ALL CROSS SECTIONS 7793 1451 30 FULLY DETERMINED BY RESONANCE PARAMETERS. IN THE 7793 1451 31 MF=3 FILE ALL CROSS SECTIONS IN THAT REGION ARE 7793 1451 32 EQUAL TO ZERO. IN THE REGION 300 EV - 100 KEV 7793 1451 33 CROSS SECTIONS CALCULATED VIA AVERAGE RESONANCE 7793 1451 34 PARAMETERS ARE ADOPTED.AVERAGE PARAMETERS WAS 7793 1451 35 CHOOSED BY FITTING EXISTED EXPERIMENTAL DATA /2/ 7793 1451 36 ON IR-193 CAPTURE CROSS SECTION IN THE REGION 7793 1451 37 3 - 100 KEV AND TOTAL CROSS SECTION IN THE REGION 7793 1451 38 300 EV - 100 KEV. 7793 1451 39 --------------------------------------------------- 7793 1451 40 ! USED AVERAGE PARAMETERS ! 7793 1451 41 !-------------------------------------------------! 7793 1451 42 ! SCATTERING RADIUS, FERMI 6.0 ! 7793 1451 43 !.................................................! 7793 1451 44 ! NEUTRON STRENGTH FUNCTION ! 7793 1451 45 ! (MULTIPLIED BY 10-4) ! 7793 1451 46 ! L=0 3.59 ! 7793 1451 47 ! L=1 1.0 ! 7793 1451 48 ! L=2 1.0 ! 7793 1451 49 !.................................................! 7793 1451 50 ! RADIATIVE STRENGTH FUNCTION ! 7793 1451 51 ! (MULTIPLIED BY 10-4) ! 7793 1451 52 ! L=0 134. ! 7793 1451 53 ! L=1 100. ! 7793 1451 54 ! L=2 100. ! 7793 1451 55 --------------------------------------------------- 7793 1451 56 CALCULATIONS ARE FULFILLED BY EVPAR CODE /3/. 7793 1451 57 MT=4 - CROSS SECTION OF PRODUCTION THE ISOMERIC STATE 7793 1451 58 OF IR-193M AT INELASTIC SCATTERING WAS ESTIMATED 7793 1451 59 BY THE TNG CODE WITH RENORMALIZATION ON THE 7793 1451 60 EXPERIMENTAL DATA /4,5,6,7/. 7793 1451 61 MT=102- RADIATIVE CROSS SECTION IN THE MF=3 FILE IN THE 7793 1451 62 REGION 10-5 EV - 300 EV PUT EQUAL TO ZERO (CROSS 7793 1451 63 SECTIONS IN THIS INTERVAL ARE DESCRIBED BY RESONANCE 7793 1451 64 PARAMETERS). FROM 10 KEV TO 2 MEV EYE GUIDE CUR- 7793 1451 65 VE BASED AN THE EXPERIMENTAL DATA COMPILED IN REF/2/ 7793 1451 66 ADOPTED HERE. ABOVE 2 MEV CROSS SECTION PUT EQUAL TO 7793 1451 67 THOSE OF AU-197 RENORMALIZED ON IR-193 EVALUATED 7793 1451 68 CAPTURE CROSS SECTION IN THE 1 - 2 MEV INTERVAL. 7793 1451 69 7793 1451 70 902=P102G, 912=P102M; 934=XS4M; 7793 1451 71 946=XS16G, 947=XS16M, 948=XS16N; 967=XS107G, 168=XS107M. 7793 1451 72 7793 1451 73 MF=8 - RADIACTIVE NUCLIDE PRODUCTION. 7793 1451 74 ----------------------------- 7793 1451 75 IN ALL SECTIONS OF THIS FILE ADOPTED NO=1. 7793 1451 76 MT=4 - AS THE RESULTS OF INELASTIC SCATTERING ONE ISOMERIC 7793 1451 77 STATE ARE PRODUCED: 7793 1451 78 IR-193 M (IG, CE; T1/2=10.6 D) 7793 1451 79 MT=16 - AS THE RESULTS OF (N,2N) REACTIONS THE NEXT RADIO- 7793 1451 80 NUCLIDES ARE PRODUCED: 7793 1451 81 IR-192 G (BETA-, EC, GAM; T1/2=74.0 D) 7793 1451 82 IR-192 M1 (IG,CE, BETA-, GAM; T1/2=1.4 M) 7793 1451 83 IR-192 M2 (IG, T1/2=241 J) 7793 1451 84 MT=17 - AS THE RESULTS OF (N,3N) REACTIONS THE NEXT RADIO- 7793 1451 85 NUCLIDE ARE PRODUCED: 7793 1451 86 IR-191 M (IG, CE; T1/2=4.94 S) 7793 1451 87 MT=102- AS THE RESULTS OF RADIATIVE CAPTURE REACTIONS THE 7793 1451 88 NEXT RADIONUCLIDES ARE PRODUCED: 7793 1451 89 IR-194 G (BETA-, GAM, T1/2=19.15 H) 7793 1451 90 IR-194 M (BETA-, GAM, T1/2=171 D) 7793 1451 91 MT=103- AS THE RESULTS OF (N,P) REACTIONS THE NEXT RADIONUC- 7793 1451 92 LIDE ARE PRODUCED: 7793 1451 93 OS-193 G (BETA-, GAM; T1/2=30.0 H) 7793 1451 94 MT=107- AS THE RESULTS OF (N,ALFA) REACTIONS THE NEXT RADIO- 7793 1451 95 NUCLIDES ARE PRODUCED: 7793 1451 96 RE-190 G (BETA-, GAM; T1/2=3.1 M) 7793 1451 97 RE-190 M (IG, CE, BETA-; T1/2=3.0 H) 7793 1451 98 MF=9 - MULTIPLICITIES FOR PRODUCTION OF RADIONUCLIDES: 7793 1451 99 ---------------------------------------------- 7793 1451 100 MT=102- PROBABILITY OF PRODACTION ISOMERIC IR-194 IN 7793 1451 101 IR-193(N,GAMMA) REACTION AT THERMAL ENERGY IS MEASU- 7793 1451 102 RED BY GOLDHABER ( SEE REF./1/). AT HIGH ENERGY THIS 7793 1451 103 PROBABILITY ACCEPTED THE SAME AS PROBABILITY OF 7793 1451 104 PRODUCTION OF LONG-LIVED ISOMER IR-192M2 IN THE 7793 1451 105 IR-191(N,GAM) REACTION.THE LAST WAS EVALUATED AS 7793 1451 106 DIFFERENCE BETWEEN TOTAL IR-191(N,GAM) AND 7793 1451 107 IR-191(N,GAM)IR-192G+M1 CROSS SECTIONS (SEE REF./2/).7793 1451 108 MF=10 - RADIONUCLIDE PRODUCTION CROSS SECTIONS 7793 1451 109 ---------------------------------------------- 7793 1451 110 MT=16 - SUMMARY CROSS SECTION OF PRODUCTION OF IR-192G+M1 7793 1451 111 IS ADOPTED IN ACCORDANCE WITH EXPERIMENTAL DATA 7793 1451 112 COMPILED IN REF /2/.PROBABILITY OF PRODUCTION OF 7793 1451 113 IR-192G IN THIS PROCESS IS ACCEPTED EQUAL TO 2/3. 7793 1451 114 PROBABILITY OF EXITATION OF THE SECOND ISOMERIC 7793 1451 115 STATE IS ADOPTED THE SAME AS FOR IR-191(N,2N) REAC- 7793 1451 116 TION.THE LAST WAS EVALUATED ON THE BASIS OF EXPE- 7793 1451 117 RIMENTAL DATA FROM REF /2/. - 7793 1451 118 MT=17 - CROSS SECTION OF PRODUCTION OF IR-191M1 IN (N,3N) 7793 1451 119 REACTION ESTIMATED IN THE SUPPOSING THAT PROBABILITY 7793 1451 120 OF PRODUCTION OF THIS ISOMER IS THE SAME AS IN THE 7793 1451 121 INELASTIC SCATTERING OF 14 MEV NEUTRONS ON IR-191, 7793 1451 122 THAT IS 60%.CROSS SECTION OF IR-193(N,3N) REACTION 7793 1451 123 IS ESTIMATED IN SUPPOSION THAT RATIO OF THIS CROSS 7793 1451 124 SECTION TO THAT OF IR-193(N,2N) IS THE SAME AS FOR 7793 1451 125 IR-191. THE LAST RATIO WAS EVALUATED ON THE BASIS OF 7793 1451 126 EXPERIMENTAL DATA FROM REF /2/. 7793 1451 127 MT=103 CROSS SECTION 0F PRODUCTION OF OS-193 IS EQUAL TO 7793 1451 128 RATIO OF CROSS SECTIONS IR-193(N,P)/IR(N,P).THESE 7793 1451 129 CROSS SECTIONS WAS CALCULATED BY TNG CODE AND RENOR- 7793 1451 130 MALISATED TO QAIM ET AL DATA /8/ AT 14.7 MEV. 7793 1451 131 MT=107- CROSS SECTION OF IR-193(N,A) REACTION IS CALCULATED 7793 1451 132 BY TNG CODE AND RENORMALISED TO KHURANA AT AL DATA 7793 1451 133 /9/ AT 14.0 MEV. 7793 1451 134 PROBABILITIES OF PRODUCTION RE-190G AND RE-190M IN 7793 1451 135 IR-193(N,ALFA) REACTION ACCEPTED EQUAL TO 2/3 AND 7793 1451 136 1/3. 7793 1451 137 7793 1451 138 REFERENCIES 7793 1451 139 7793 1451 140 1.NEUTRON CROSS SECTIONS. V1. NEUTRON RESONANCE PARAMETERS AND 7793 1451 141 THERMAL CROSS SECTIONS. PART B. S.F.MUGHABGHAB, M.DIVADEENAM, 7793 1451 142 N.E.HOLDEN. NNDC BNL, ACADEMIC PRESS 1981. 7793 1451 143 2.NEUTRON CROSS SECTIONS. V2. NEUTRON CROSS SECTIONS CURVES. 7793 1451 144 V.MCLANE, C.L.DUNFORD, P.F.ROSE. NNDC BNL, ACADEMIC PRESS 1988. 7793 1451 145 3.MANTUROV G.N. ET AL. VANT "YADENYE CONSTANTY" ISSUE 1(50),P.50. 7793 1451 146 MOSKOV, 1983. 7793 1451 147 4.BROADHEAD ET AL. INT.J. OF APPLIED RADIATION AND ISOTOPS. V.18, 7793 1451 148 P.279, 1967. 7793 1451 149 5.BORNEMISZA ET AL. ATOMIK KOZLEMENYEK, V.10(2),P.112. DEBREZEN, 7793 1451 150 1968. 7793 1451 151 6.ANDERS ET AL. PROC. OF INT. CONF. NUCL. DATA FOR SCIENCE AND 7793 1451 152 TECHN. ANTWERP, 1982, P.859. 7793 1451 153 7.BAYHURST ET AL. PHYS.REV./C. V.12, P.451, 1975. 7793 1451 154 8.QAIM ET AL. NUCL.PHYS/A.V.283, P.269, 1977. 7793 1451 155 9.KHURANA ET AL. PROC. OF LOWENERGY NUCLEAR PHYS.SYMP.WALTAIR, 7793 1451 156 P.297,1960. 7793 1451 157 7793 1451 158 ***************************************************************** 7793 1451 159 7793 1451 160 1 451 187 07793 1451 161 2 151 50 07793 1451 162 3 4 15 07793 1451 163 3 16 11 07793 1451 164 3 17 6 07793 1451 165 3 102 18 07793 1451 166 3 103 7 07793 1451 167 3 107 8 07793 1451 168 3 902 7 07793 1451 169 3 912 7 07793 1451 170 3 934 15 07793 1451 171 3 946 11 07793 1451 172 3 947 10 07793 1451 173 3 948 9 07793 1451 174 3 967 8 07793 1451 175 3 968 8 07793 1451 176 4 16 2 07793 1451 177 4 17 2 07793 1451 178 8 4 2 07793 1451 179 8 16 4 07793 1451 180 8 17 2 07793 1451 181 8 102 3 07793 1451 182 8 103 2 07793 1451 183 8 107 3 07793 1451 184 9 102 13 07793 1451 185 10 16 28 07793 1451 186 10 107 15 07793 1451 187 7793 1 099999 7793 0 0 0 7.71930+ 4 1.91305+ 2 0 0 1 07793 2151 1 7.71930+ 4 1.00000+ 0 0 0 1 07793 2151 2 1.00000- 5 3.00000+ 2 1 2 0 07793 2151 3 1.50000+ 0 1.13000+ 0 0 0 1 07793 2151 4 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2.00000+ 6 6.23604- 1 2.50000+ 6 7.30163- 1 3.00000+ 6 8.20491- 17793 3 4 10 5.00000+ 6 1.12026+ 0 7.00000+ 6 1.31579+ 0 7.80600+ 6 1.58260+ 07793 3 4 11 8.00000+ 6 1.60837+ 0 9.00000+ 6 1.33971+ 0 1.00000+ 7 8.69219- 17793 3 4 12 1.10000+ 7 7.17703- 1 1.20000+ 7 3.50877- 1 1.30000+ 7 2.23285- 17793 3 4 13 1.40000+ 7 1.59490- 1 1.50000+ 7 1.43541- 1 1.60000+ 7 1.27592- 17793 3 4 14 2.00000+ 7 9.56938- 2 7793 3 4 15 7793 3 099999 7.71930+ 4 1.91305+ 2 0 0 0 07793 3 16 1 -7.76500+ 6-7.76500+ 6 0 0 1 227793 3 16 2 22 2 7793 3 16 3 7.80559+ 6 .00000+ 0 7.86419+ 6 1.43047- 2 7.96743+ 6 3.99547- 27793 3 16 4 8.00000+ 6 4.78469- 2 8.11200+ 6 1.05469- 1 8.13900+ 6 1.18346- 17793 3 16 5 8.15500+ 6 1.25855- 1 8.28800+ 6 2.64972- 1 9.00000+ 6 7.97847- 17793 3 16 6 1.00000+ 7 1.41179+ 0 1.10000+ 7 1.84815+ 0 1.20000+ 7 2.07217+ 07793 3 16 7 1.30000+ 7 2.20089+ 0 1.40000+ 7 2.23006+ 0 1.40370+ 7 2.22807+ 07793 3 16 8 1.44400+ 7 2.13022+ 0 1.50000+ 7 2.09489+ 0 1.60000+ 7 1.90421+ 07793 3 16 9 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