IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 7.71910+ 4 1.89320+ 2 1 0 0 27791 1451 1 0.00000+ 0 0.00000+ 0 0 0 0 67791 1451 2 1.00000+ 0 2.00000+ 7 0 0 10 937791 1451 3 0.00000+ 0 0.00000+ 0 0 0 167 317791 1451 4 77-Ir-191 FEI EVAL-JAN90 NIKOLAEV M.N. 7791 1451 5 REF.SEE MT=451 DIST- REV1-NOV93 9318017791 1451 6 ----FOND-2 MATERIAL 7791 7791 1451 7 -----INCIDENT NEUTRON ACTIVATION DATA 7791 1451 8 ------ENDF-6 FORMAT 7791 1451 9 7791 1451 10 ***************************************************************** 7791 1451 11 7791 1451 12 RESULTS OF EVALUATION FULFILLED BY NIKOLAEV M.N. 7791 1451 13 DATA COMPILED AND CHECKED BY G.V.SAVOSKINA. 7791 1451 14 7791 1451 15 7791 1451 16 COMMENTS TO CONTENT: 7791 1451 17 MF=1 7791 1451 18 MT=451. DESCRIPTION IS WRITTED DOWN BY NIKOLAEV M.N. 7791 1451 19 MF=2 - RESONANCE REGION. 7791 1451 20 ----------------- 7791 1451 21 MT=151. RESOLVED RESONANCE REGION EXTENTS FOR IR-191 TO 7791 1451 22 160 EV (BOUND LEVEL +45 S-RESONANCES +5 ARTIFICAL 7791 1451 23 S-RESONANCES OUT OF THE REGION) .RESONANCE PA- 7791 1451 24 RAMETERS ARE TAKEN FROM /1/. ARTIFICAL RESONANCES 7791 1451 25 USED FOR TAKING INTO ACCOUNT UNRESOLVED RESONANCES 7791 1451 26 CONTRIBUTIONS. THEIR ENERGIES ARE TAKEN FROM /1/. 7791 1451 27 AVERAGE WIDTHS ARE ADOPTED FOR ARTIFICAL RESONANCES. 7791 1451 28 MF=3 - CROSS-SECTIONS. 7791 1451 29 -------------- 7791 1451 30 IN THE REGION 0.00001 -160 EV ALL CROSS SECTIONS 7791 1451 31 FULLY DETERMINED BY RESONANCE PARAMETERS. IN THE 7791 1451 32 MF=3 FILE ALL CROSS SECTIONS IN THAT REGION ARE 7791 1451 33 EQUAL TO ZERO. IN THE REGION 160EV - 100 KEV 7791 1451 34 CROSS SECTION CALCULATED VIA 7791 1451 35 THE AVERAGED RESONANCE PARAMETERS ARE ADOPTED. AVE- 7791 1451 36 RAGED PARAMETERS WAS CHOOSED BY FITTING EXISTED 7791 1451 37 EXPERIMENTAL DATA /2/ ON IR-191 CAPTURE 7791 1451 38 CROSS SECTION IN THE REGION 3 - 100 KEV INTERVAL 7791 1451 39 AND TOTAL CROSS SECTION DATA IN THE REGION 300 EV - 7791 1451 40 100 KEV. 7791 1451 41 ----------------------------------------- 7791 1451 42 ! USED AVERAGED PARAMETERS ! IR-191 ! 7791 1451 43 !---------------------------------------- 7791 1451 44 ! SCATTERING RADIUS, FERMI 5.7 ! 7791 1451 45 !........................................! 7791 1451 46 ! NEUTRON STRENGTH FUNCTION ! 7791 1451 47 ! (MULTIPLIED BY 10-4) ! 7791 1451 48 ! L=0 3.37 ! 7791 1451 49 ! L=1 1.0 ! 7791 1451 50 ! L=2 1.0 ! 7791 1451 51 !........................................! 7791 1451 52 ! RADIATIVE STRENGTH FUNCTION ! 7791 1451 53 ! (MULTIPLIED BY 10-4) ! 7791 1451 54 ! L=0 240. ! 7791 1451 55 ! L=1 100. ! 7791 1451 56 ! L=2 100. ! 7791 1451 57 ------------------------------------------ 7791 1451 58 CALCULATIONS ARE FULFILLED BY EVPAR CODE /3/. 7791 1451 59 MT=4 - CROSS SECTIONS OF PRODUCTION OF ISOMERIC STATE 7791 1451 60 IR-191M AT INELASTIC SCATTERING ARE 7791 1451 61 ESTIMATED BY TNG CODE WITH RENORMALISATION TO THE 7791 1451 62 EXPERIMENTAL DATA /4,6,7,8/. 7791 1451 63 MT=16 - IS THE SUM OF SUBSECTIONS OF FILE 10. 7791 1451 64 MT=17 - (N,3N) REACTION CROSS SECTION FOR IR-191 IS ADOPTED 7791 1451 65 IN ACCORDANCE WITH EXPERIMENTAL DATA CITED IN REF./2/7791 1451 66 MT=102- RADIATIVE CROSS SECTION IN THE MF=3 FILE IN THE 7791 1451 67 REGION 10-5 EV - 160 EV PUT EQUAL TO ZERO (CROSS 7791 1451 68 SECTIONS IN THIS INTERVAL ARE DESCRIBED BY RESONANCE 7791 1451 69 PARAMETERS); IN THE REGION 160 EV - 100 KEV 7791 1451 70 CAPTURE CROSS SECTION OF IR-191 IS CALCULATED 7791 1451 71 ON THE BASIS OF AVERAGED RESONANCE PARAMETERS; 7791 1451 72 FROM 10 KEV TO 2 MEV EYE GUIDE CURVE 7791 1451 73 BASED AN THE EXPERIMENTAL DATA COMPILED IN REF/2/. 7791 1451 74 ADOPTED HERE. ABOVE 2 MEV CROSS SECTION PUT EQUAL TO 7791 1451 75 THOSE OF AU-197 RENORMALIZED ON IR-191 EVALUATED 7791 1451 76 CAPTURE CROSS SECTION IN THE 1 - 2 MEV INTERVAL. 7791 1451 77 MT=103- IS THE SUM OF SUBSECTIONS OF FILE 10. 7791 1451 78 MT=107- IS THE SUM OF SUBSECTIONS OF FILE 10. 7791 1451 79 7791 1451 80 902=P102G, 912=P102M, 922=P102N; 934=XS4M; 946=XS16G, 947=XS16M,7791 1451 81 948=XS16N; 953=XS103G, 954=XS103M; 967=XS107G, 968=XS107M. 7791 1451 82 7791 1451 83 MF=8 - RADIACTIVE NUCLIDE PRODUCTION. 7791 1451 84 ----------------------------- 7791 1451 85 IN ALL SECTIONS OF THIS FILE ADOPTED NO=1. 7791 1451 86 MT=4 - AS THE RESULTS OF INELASTIC SCATTERING ONE ISOMERIC 7791 1451 87 STATE ARE PRODUCED: 7791 1451 88 IR-191 M (IG, CE; T1/2=4.94 S) 7791 1451 89 MT=16 - AS THE RESULTS OF (N,2N) REACTIONS THE NEXT RADIO- 7791 1451 90 NUCLIDES ARE PRODUCED: 7791 1451 91 IR-190 G (EC, GAM; T1/2=11.8 D) 7791 1451 92 IR-190 M1 (IG, BETA-; T1/2=1,2 H) 7791 1451 93 IR-190 M2 (IG, CE; T1/2=3.1 H) 7791 1451 94 MT=17 - AS THE RESULTS OF (N,3N) REACTIONS THE NEXT RADIO- 7791 1451 95 NUCLIDE ARE PRODUCED: 7791 1451 96 IR-189 (EC, GAM; T1/2=13.3 D) 7791 1451 97 MT=102- AS THE RESULTS OF RADIATIVE CAPTURE REACTIONS THE 7791 1451 98 NEXT RADIONUCLIDES ARE PRODUCED: 7791 1451 99 IR-192 G (BETA-, EC, GAM; T1/2=3.1 H) 7791 1451 100 IR-192 M1 (IG, CE, BETA-, GAM; T1/2=1.4 M) 7791 1451 101 IR-192 M2 (IG, T1/2=241 J) 7791 1451 102 MT=103- AS THE RESULTS OF (N,P) REACTIONS THE NEXT RADIONUC- 7791 1451 103 LIDES ARE PRODUCED: 7791 1451 104 OS-191 G (BETA-, T1/2=15.4 D) 7791 1451 105 OS-191 M (IG,CE,T1/2=13.1 H) 7791 1451 106 MT=107- AS THE RESULTS OF (N,ALFA) REACTIONS THE NEXT RADIO- 7791 1451 107 NUCLIDES ARE PRODUCED: 7791 1451 108 RE-188 G (BETA-, GAM; T1/2=16.98 H) 7791 1451 109 RE-188 M (IG, CE; T1/2=18.6 M) 7791 1451 110 MF=9 - MULTIPLICITIES FOR PRODUCTION OF RADIONUCLIDES: 7791 1451 111 ---------------------------------------------- 7791 1451 112 MT=102- PROBABILITIES OF PRODUCTION GROUND (4-) AND ISOMERIC 7791 1451 113 STATES (1+ AND 9+) OF IR-192 IN IR-191(N,GAMMA) RE- 7791 1451 114 ACTION AT THERMAL ENERGY WAS MEASURED EXPERIMENTALLY 7791 1451 115 AND ACCEPTED IN THE ACCORDANCE WITH RECOMMENDATION 7791 1451 116 OF /4 /. AT HIGH ENERGY PROBABILITY OF FORMATION OF 7791 1451 117 LONG LIVED ISOMER ESTIMATED AS THE DIFFERENSE BETWE- 7791 1451 118 EN TOTAL IR-191(N,GAMMA) AND IR-191(N,GAMMA)IR-192G+ 7791 1451 119 +M1 CROSS SECTIONS EVALUATED IN /2/. PROBABILITY 7791 1451 120 OF FORMATION OF SHORT LIVED ISOMER EVALUATED ON 7791 1451 121 THE BASIS OF DATA SIDDAPPA ET AL /5 / AT 25 KEV. IT 7791 1451 122 IS SUPPOSED THAT CITED IN THE EXFOR DATA OF THIS 7791 1451 123 WORK ARE 10 TIMES TOO HIGH (ANALOGOUS "UNCERTANTIES" 7791 1451 124 OF THIS WORK TAKE PLACE AND FOR OTHER MATERIALS). 7791 1451 125 MF=10 - RADIONUCLIDES PRODUCTION CROSS SECTIONS 7791 1451 126 ---------------------------------------------- 7791 1451 127 MT=16 - (N,2N) CROSS SECTION IS ADOPTED IN ACCORDANCE WITH 7791 1451 128 EXPERIMENTAL DATA COMPILED IN REF. /2/ FOR 7791 1451 129 IR-191(N,2N)IR-190G+M1 AND IR-191(N,2N)IR-190M2 . 7791 1451 130 CROSS SECTION OF PRODUCTION OF IR-190G ACCEPTED EQUAL7791 1451 131 TO 2/3 FROM THOS OF IR-191(N,2N)IR-190G+M1. 7791 1451 132 THE REST IS PRODUCTION OF IR-190M1. PROBABILITY OF 7791 1451 133 PRODUCTION OF IR-190M2 DETERMINED AS RATIO CORRES- 7791 1451 134 PONDING CROSS SECTION TO THE TOTAL (N,2N) CROSS 7791 1451 135 MT=103- CROSS SECTION OF (N,P) REACTION IS CALCULATED BY TNG 7791 1451 136 CODE AND RENORMALIZED ON QAIM ET AL /9/ EXPERIMENTAL 7791 1451 137 DATA AT 14.7 MEV. 7791 1451 138 PROBABILITIES OF PRODUCTION OF OS-191G AND OS-191M 7791 1451 139 IN THE IR-191(N,P) REACTION ACCEPTED EQUAL TO THAT 7791 1451 140 FOR RADIATIVE CAPTURE OF THERMAL NEUTRONS IN OS-190. 7791 1451 141 MT=107- CROSS SECTION OF (N,ALFA) REACTION IS CALCULATED BY 7791 1451 142 TNG CODE AND RENORMALIZED FOR IR-191 ON THE COLEMAN 7791 1451 143 ET AL /10 / EXPERIMENTAL DATA AT 14.5 MEV. 7791 1451 144 PROBABILITIES OF PRODUCTION OF RE-188G AND RE-188M 7791 1451 145 IN IR-191(N,ALFA) REACTION ACCEPTED EQUAL TO THAT 7791 1451 146 FOR RADIATIVE CAPTURE OF THERMAL NEUTRONS IN RE-187. 7791 1451 147 7791 1451 148 REFERENCIES 7791 1451 149 7791 1451 150 1.NEUTRON CROSS SECTIONS. V1. NEUTRON RESONANCE PARAMETERS AND 7791 1451 151 THERMAL CROSS SECTIONS. PART B. S.F.MUGHABGHAB, M.DIVADEENAM, 7791 1451 152 N.E.HOLDEN. NNDC BNL, ACADEMIC PRESS 1981. 7791 1451 153 2.NEUTRON CROSS SECTIONS. V2. NEUTRON CROSS SECTIONS CURVES. 7791 1451 154 V.MCLANE, C.L.DUNFORD, P.F.ROSE. NNDC BNL, ACADEMIC PRESS 1988. 7791 1451 155 3.MANTUROV G.N. ET AL. VANT "YADENYE CONSTANTY" ISSUE 1(50),P.50. 7791 1451 156 MOSKOV, 1983. 7791 1451 157 4.ANDERS ET AL. PROC. OF INT. CONF. NUCL. DATA FOR SCIENCE AND 7791 1451 158 TECHN. ANTWERP, 1982, P.859. 7791 1451 159 5.SIDDAPPA ET AL. PROC. OF NUCL. AND SOLID STATE PHYS. SIMP. 7791 1451 160 MADARAI. 1970, V.2, P.29. 7791 1451 161 6.BROADHEAD ET AL. INT.J. OF APPLIED RADIATION AND ISOTOPS. V.18, 7791 1451 162 P.279, 1967. 7791 1451 163 7.BORNEMISZA ET AL. ATOMIK KOZLEMENYEK, V.10(2),P.112. DEBREZEN, 7791 1451 164 1968. 7791 1451 165 8.BAYHURST ET AL. PHYS.REV./C. V.12, P.451, 1975. 7791 1451 166 9.QAIM ET AL. NUCL.PHYS/A.V.283, P.269, 1977. 7791 1451 167 10.COLEMAN ET AL. PROC.PHYS.SOC. K.73,P.218, 1959. 7791 1451 168 7791 1451 169 ***************************************************************** 7791 1451 170 7791 1451 171 1 451 202 07791 1451 172 2 151 56 07791 1451 173 3 4 11 07791 1451 174 3 16 8 07791 1451 175 3 17 6 07791 1451 176 3 102 19 07791 1451 177 3 103 7 07791 1451 178 3 107 8 07791 1451 179 3 902 8 07791 1451 180 3 912 8 07791 1451 181 3 922 8 07791 1451 182 3 934 11 07791 1451 183 3 946 8 07791 1451 184 3 947 8 07791 1451 185 3 948 8 07791 1451 186 3 953 7 07791 1451 187 3 954 7 07791 1451 188 3 967 8 07791 1451 189 3 968 8 07791 1451 190 4 16 2 07791 1451 191 4 17 2 07791 1451 192 8 4 2 07791 1451 193 8 16 4 07791 1451 194 8 17 2 07791 1451 195 8 102 4 07791 1451 196 8 103 3 07791 1451 197 8 107 3 07791 1451 198 9 102 22 07791 1451 199 10 16 22 07791 1451 200 10 103 13 07791 1451 201 10 107 15 07791 1451 202 7791 1 099999 7791 0 0 0 7.71910+ 4 1.89320+ 2 0 0 1 07791 2151 1 7.71910+ 4 1.00000+ 0 0 0 1 07791 2151 2 1.00000- 5 1.60000+ 2 1 2 0 07791 2151 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