                             95 - Am - 242m                       9542 0  0    0
 9.52420+04 2.39980+02          1          1          0          19542 1451    1
 4.86300+04 1.00000+00          3          1          0          69542 1451    2
 1.00000+00 0.00000+00          0          0         10          69542 1451    3
 0.00000+00 0.00000+00          0          0        172         819542 1451    4
 95-Am-242M MINSK BYEL    EVAL-DEC96                              9542 1451    5
                          DIST-DEC96                              9542 1451    6
                                                                  9542 1451    7
                      V.M. MASLOV, E.Sh. SUKHOVITSKIJ,            9542 1451    8
                      Yu.V. PORODZINSKIJ, G.B. MOROGOVSKIJ        9542 1451    9
                                                                  9542 1451   10
 STATUS                                                           9542 1451   11
 EVALUATION WAS MADE UNDER THE PROJECT AGREEMENT CIS-03-95        9542 1451   12
 WITH INTERNATIONAL SCIENCE AND TECHNOLOGY CENTER (MOSCOW).       9542 1451   13
 FINANCING PARTY OF THE ISTC FOR THE PROJECT IS JAPAN.            9542 1451   14
 EVALUATION WAS REQUESTED BY Y.KIKUCHI (JAERI, TOKAI)             9542 1451   15
 DOCUMENTED IN INDC(BLR)-007, 1997.                               9542 1451   16
                                                                  9542 1451   17
 MF=1   GENERAL  INFORMATION                                      9542 1451   18
                                                                  9542 1451   19
   MT=451  COMMENTS AND DICTIONARY                                9542 1451   20
   MT=452  TOTAL NUMBER OF NEUTRONS PER FISSION                   9542 1451   21
           SUM OF MT=455 AND MT=456.                              9542 1451   22
   MT=455  DELAYED NEUTRON DATA                                   9542 1451   23
           NUMBER OF DELAYED NEUTRONS AND                         9542 1451   24
           DECAY CONSTANTS FROM BRADY ET AL./1/                   9542 1451   25
   MT=456  NUMBER OF PROMPT NEUTRONS PER FISSION                  9542 1451   26
           MADLAND-NIX MODEL CALCULATIONS /2/ FITTED TO           9542 1451   27
           THE MEASURED DATA OF HOWE ET AL./3/                    9542 1451   28
           ABOVE  EMISSIVE FISSION THRESHOLD                      9542 1451   29
           SUPERPOSITION OF NEUTRON EMISSION                      9542 1451   30
           IN (N,XNF) REACTIONS /4/ AND PROMPT FISSION            9542 1451   31
           NEUTRONS IS EMPLOYED.                                  9542 1451   32
                                                                  9542 1451   33
 MF=2   RESONANCE PARAMETERS                                      9542 1451   34
                                                                  9542 1451   35
   MT=151  RESONANCE  PARAMETERS  (MLBW)                          9542 1451   36
           RESOLVED RESONANCE REGION :     1.0E-5 - 43 EV         9542 1451   37
           PARAMETERS FOR BREIT-WIGNER FORMULA ARE BASED UPON     9542 1451   38
           THE FISSION CROSS SECTION MEASUREMENTS OF BROWNE ET AL.9542 1451   39
           /5/                                                    9542 1451   40
           CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE       9542 1451   41
           INTEGRALS ARE:                                         9542 1451   42
                            2200 M/SEC       RES.INTEG.           9542 1451   43
              TOTAL         7624.69 b            -                9542 1451   44
              ELASTIC        5.2526 b            -                9542 1451   45
              FISSION       6390.21 b         1543.91             9542 1451   46
              CAPTURE       1229.23 b         239.610             9542 1451   47
                                                                  9542 1451   48
           UNRESOLVED RESONANCE REGION :                          9542 1451   49
           ENERGY INDEPENDENT PARAMETERS:                         9542 1451   50
              R=9.1677  FM  FROM OPTICAL MODEL CALCULATIONS       9542 1451   51
              S1=2.020*10-4  FROM OPTICAL MODEL CALCULATIONS      9542 1451   52
              S2=1.540*10-4  FROM OPTICAL MODEL CALCULATIONS      9542 1451   53
           ENERGY   DEPENDENT PARAMETERS:                         9542 1451   54
           S0-DECREASES FROM 1.215-4(0.15KEV) TO 1.15-4(27.28KEV),9542 1451   55
           BELOW 0.1 KEV FLUCTUATES TO FIT FISSION CROSS SECTION. 9542 1451   56
           D - SPIN DEPENDENT, NORMALIZED TO <Dobs> =0.271 EV     9542 1451   57
           WITH ACCOUNT OF LEVEL MISSING /6/.                     9542 1451   58
           WF -SPIN DEPENDENT AS DEFINED BY THE TRANSITION STATE  9542 1451   59
           SPECTRA AT INNER AND OUTER BARRIER HUMPS, NORMALIZED   9542 1451   60
           TO <WFobs>=0.395 mEV TO FIT UNRESOLVED RESONANCE REGION9542 1451   61
           EXPERIMENTAL FISSION DATA /5/.                         9542 1451   62
           WG - FROM CASCADE MODEL WITH ACCOUNT OF FISSION AND    9542 1451   63
           NEUTRON EMISSION COMPETITION, SPIN DEPENDENT. NORMA-   9542 1451   64
           LIZED TO <WGobs>= 0.050 EV.                            9542 1451   65
                                                                  9542 1451   66
 MF=3   NEUTRON CROSS SECTIONS                                    9542 1451   67
                                                                  9542 1451   68
   MT=1,4,51-75,91,102.  TOTAL, ELASTIC AND INELASTIC             9542 1451   69
           SCATTERING, CAPTURE CROSS SECTION                      9542 1451   70
           TOTAL,DIRECT ELASTIC AND DIRECT INELASTIC FOR MT=55,   9542 1451   71
           59 AND OPTICAL TRANSMISSION COEFFICIENTS FROM          9542 1451   72
           COUPLED CHANNELS CALCULATIONS.                         9542 1451   73
           THE DEFORMED OPTICAL POTENTIAL USED:                   9542 1451   74
           VR=(46.10-0.3*E) MEV    RR=1.26 FM  AR=0.615 FM        9542 1451   75
           WD=(3.53+0.4*E)  MEV  E <  10 MEV    RD=1.24 FM        9542 1451   76
           WD= 7.50 MEV          E=>  10 MEV    AD=0.5 FM         9542 1451   77
           VSO=6.2 MEV RSO=1.12 FM ASO=0.47 FM  B2=0.206 B4=0.092 9542 1451   78
           THREE LEVELS OF METASTABLE STATE ROTATIONAL BAND       9542 1451   79
           ARE COUPLED.                                           9542 1451   80
           CAPTURE,COMPOUND ELASTIC AND INELASTIC BY STATISTICAL  9542 1451   81
           MODEL, SEE MT=18-21                                    9542 1451   82
           ABOVE NEUTRON ENERGY 5 MEV CAPTURE IS ASSUMED TO BE    9542 1451   83
           CONSTANT.                                              9542 1451   84
           ADOPTED LEVEL SCHEME OF AM-242 FROM NUCLEAR DATA       9542 1451   85
           SHEETS /7/.                                            9542 1451   86
                                                                  9542 1451   87
             No       ENERGY(MEV)     SPIN-PARITY   K             9542 1451   88
                                                                  9542 1451   89
            g.s.       0.0               5   -      0             9542 1451   90
             1        -0.04863           1   -      0             9542 1451   91
             2        -0.00453           0   -      5             9542 1451   92
             3         0.00427           3   -      0             9542 1451   93
             4         0.02717           2   -      0             9542 1451   94
             5         0.06537           6   -      5             9542 1451   95
             6         0.09137           6   -      6             9542 1451   96
             7         0.09937           5   -      0             9542 1451   97
             8         0.10127           4   -      0             9542 1451   98
             9         0.14137           7   -      5             9542 1451   99
            10         0.14897           3   -                    9542 1451  100
            11         0.16837           7   -      6             9542 1451  101
            12         0.17137           1   -      1             9542 1451  102
            13         0.18187           2   +      1             9542 1451  103
            14         0.19337           2   -      1             9542 1451  104
            15         0.19547           3   -      3             9542 1451  105
            16         0.21437           6   -      0             9542 1451  106
            17         0.21447           7   -      0             9542 1451  107
            18         0.22147           2   +                    9542 1451  108
            19         0.22637           3   -      1             9542 1451  109
            20         0.23467           3   +                    9542 1451  110
            21         0.23977           4   -      3             9542 1451  111
            22         0.24317           2   -      2             9542 1451  112
            23         0.25637           8   -      6             9542 1451  113
            24         0.25827           3   -                    9542 1451  114
            25         0.27037           4   -      1             9542 1451  115
                                                                  9542 1451  116
                                                                  9542 1451  117
          OVERLAPPING LEVELS ARE ASSUMED ABOVE 0.273 MEV          9542 1451  118
          LEVEL DENSITY PARAMETERS: SEE MT 18-21                  9542 1451  119
   MT=16,17.  (N,2N) AND (N,3N) CROSS SECTION                     9542 1451  120
          FROM STATISTICAL MODEL CALCULATIONS /8/  WITH THE       9542 1451  121
          ACCOUNT OF PRE-EQUILIBRIUM NEUTRON EMISSION:SEE MT=18-219542 1451  122
   MT=18,19,20,21.  FISSION CROSS SECTION IS CALCULATED WITHIN    9542 1451  123
          STATISTICAL MODEL /9,10/,  THE MEASURED DATA OF:        9542 1451  124
          BROWNE  ET AL./5/ AND FURSOV ET AL./11/                 9542 1451  125
          ARE FITTED.                                             9542 1451  126
          THE FIRST CHANCE FISSION MT=19 IS CALCULATED WITH       9542 1451  127
          THE CONTRIBUTION OF EMISSIVE FISSION TO TOTAL FISSION   9542 1451  128
          CROSS SECTION ACCORDING TO /9,12/.                      9542 1451  129
                                                                  9542 1451  130
 MF=4   ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS               9542 1451  131
                                                                  9542 1451  132
        FOR MT=2, 55, 59  FROM COUPLED CHANNELS CALCULATIONS      9542 1451  133
        WITH ADDED ISOTROPIC STATISTICAL CONTRIBUTION.            9542 1451  134
                                                                  9542 1451  135
        MT=16,17,18-21,51-54,56-58,60-66,91 - ISOTROPIC           9542 1451  136
                                                                  9542 1451  137
 MF=5   ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                9542 1451  138
                                                                  9542 1451  139
        ENERGY DISTRIBUTIONS FOR MT=16,17 WERE                    9542 1451  140
        CALCULATED BY STATISTICAL MODEL OF CASCADE NEUTRON        9542 1451  141
        EMISSION TAKING INTO ACCOUNT THE HISTORY OF THE DECAY     9542 1451  142
        WITH THE ALLOWANCE OF PRE-EQUILLIBRIUM EMISSION OF        9542 1451  143
        THE FIRST NEUTRON /4/                                     9542 1451  144
        ENERGY DISTRIBUTIONS FOR MT=18,19,20,21 WERE CALCULATED   9542 1451  145
        BY MADLAND-NIX MODEL /2/ WITH ACCOUNT OF COMPETITION      9542 1451  146
        BETWEEN MULTIPLE-CHANCE FISSION PROCESSES UP THROUGH      9542 1451  147
        THIRD-CHANCE FISSION WITH THE ALLOWANCE OF PRE-EQUILIBRIUM9542 1451  148
        EMISSION OF THE FIRST NEUTRON /4,8/                       9542 1451  149
                                                                  9542 1451  150
REFERENCES                                                        9542 1451  151
                                                                  9542 1451  152
 1. Brady M.C., Wright R.Q., England T.R., Report                 9542 1451  153
    ORNL/CSD/TM-226(1991), IAEA-NDS-102, 1992.                    9542 1451  154
 2. Madland D.G., Nix J.R., Nucl. Sci. Engng. 81, 213 (1982).     9542 1451  155
 3. Howe R.E., Browne J.C., Dougan R.J., Dupzyk R.J., Landrum J.H.9542 1451  156
    Nucl. Sci. Eng.,77, 454 (1984).                               9542 1451  157
 4. Maslov V.M., Porodzinskij Yu.V., Sukhovitskij E.Sh., Proc.    9542 1451  158
    Int. Conf. on Neutron Physics, 14-18 Sept., Kiev, USSR,       9542 1451  159
    V.1, p.413, 1988.                                             9542 1451  160
 5. Browne J.C., White R.M., Howe R.E. et al., Phys. Rev. C,      9542 1451  161
    29, 2188 (1984).                                              9542 1451  162
 6. Porodzinskij Yu.V., Sukhovitskij E.Sh., Nuclear Constants,    9542 1451  163
    4, p.27, 1987 (in Russian).                                   9542 1451  164
 7. ENSDF, 1995.                                                  9542 1451  165
 8. Ignatjuk A.V., Maslov V.M., Pashchenko A.B. Sov. J. Nucl.     9542 1451  166
    Phys. 47, 224 (1988).                                         9542 1451  167
 9. Ignatjuk A.V., Maslov V.M., Proc. Int. Symp. Nuclear Data     9542 1451  168
    Evaluation Methodology, Brookhaven, USA, October 12-16, 1992, 9542 1451  169
    p.440, World Scientific, 1993.                                9542 1451  170
10. Maslov V.M. Sov. J. At. Energy 64, 478 (1988).                9542 1451  171
11. Fursov B.I., Samylin B.F., Smirenkin G.N., Polynov V.N.,      9542 1451  172
    Nuclear Data for Science and Technology, Proc. Int. Conf.,    9542 1451  173
    Gatlinburg, Tennessee, USA, May 9-13, 1994, v.1,p.269.        9542 1451  174
12. Maslov V.M., Kikuchi Y. JAERI-Research 96-030, 1996.          9542 1451  175
                                                                  9542 1451  176
                                1        451        248          19542 1451  177
                                1        452          7          19542 1451  178
                                1        455          7          19542 1451  179
                                1        456          7          19542 1451  180
                                2        151        560          19542 1451  181
                                3          1         30          19542 1451  182
                                3          2         27          19542 1451  183
                                3          4         30          19542 1451  184
                                3         16          9          19542 1451  185
                                3         17          7          19542 1451  186
                                3         18         27          19542 1451  187
                                3         19         27          19542 1451  188
                                3         20         10          19542 1451  189
                                3         21          8          19542 1451  190
                                3         51         24          19542 1451  191
                                3         52         23          19542 1451  192
                                3         53         23          19542 1451  193
                                3         54         21          19542 1451  194
                                3         55         25          19542 1451  195
                                3         56         18          19542 1451  196
                                3         57         18          19542 1451  197
                                3         58         17          19542 1451  198
                                3         59         22          19542 1451  199
                                3         60         17          19542 1451  200
                                3         61         16          19542 1451  201
                                3         62         16          19542 1451  202
                                3         63         16          19542 1451  203
                                3         64         15          19542 1451  204
                                3         65         15          19542 1451  205
                                3         66         14          19542 1451  206
                                3         67         14          19542 1451  207
                                3         68         14          19542 1451  208
                                3         69         13          19542 1451  209
                                3         70         13          19542 1451  210
                                3         71         13          19542 1451  211
                                3         72         12          19542 1451  212
                                3         73         12          19542 1451  213
                                3         74         12          19542 1451  214
                                3         75         11          19542 1451  215
                                3         91         16          19542 1451  216
                                3        102         22          19542 1451  217
                                4          2         85          19542 1451  218
                                4         16          2          19542 1451  219
                                4         17          2          19542 1451  220
                                4         18          2          19542 1451  221
                                4         19          2          19542 1451  222
                                4         20          2          19542 1451  223
                                4         21          2          19542 1451  224
                                4         51          2          19542 1451  225
                                4         52          2          19542 1451  226
                                4         53          2          19542 1451  227
                                4         54          2          19542 1451  228
                                4         55         84          19542 1451  229
                                4         56          2          19542 1451  230
                                4         57          2          19542 1451  231
                                4         58          2          19542 1451  232
                                4         59         79          19542 1451  233
                                4         60          2          19542 1451  234
                                4         61          2          19542 1451  235
                                4         62          2          19542 1451  236
                                4         63          2          19542 1451  237
                                4         64          2          19542 1451  238
                                4         65          2          19542 1451  239
                                4         66          2          19542 1451  240
                                4         67          2          19542 1451  241
                                4         68          2          19542 1451  242
                                4         69          2          19542 1451  243
                                4         70          2          19542 1451  244
                                4         71          2          19542 1451  245
                                4         72          2          19542 1451  246
                                4         73          2          19542 1451  247
                                4         74          2          19542 1451  248
                                4         75          2          19542 1451  249
                                4         91          2          19542 1451  250
                                5         16        261          19542 1451  251
                                5         17         88          19542 1451  252
                                5         18        554          19542 1451  253
                                5         19        487          19542 1451  254
                                5         20        388          19542 1451  255
                                5         21        255          19542 1451  256
                                5         91        225          19542 1451  257
                                                                  9542 1  0  258
