42-Mo- 0

 42-MO-  0 JNDC,JAERI EVAL-MAR89 JNDC FPND W.G., M.MIZUMOTO       
                      DIST-OCT89 REV2-FEB94                       
----JENDL-3.2         MATERIAL 4200                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
84-10 PHOTON PRODUCTION DATA WERE EVALUATED BY M.MIZUMOTO(JAERI). 
89-03 FINAL DATA FOR JENDL-3 WERE COMPILED FROM ISOTOPE DATA.  THE
      ISOTOPE DATA WERE EVALUATED BY JNDC FP NUCLEAR DATA WORKING 
      GROUP/1/.                                                   
90-10 MF=5: SPECTRA AT THRESHOLD ENERGIES WERE MODIFIED.          
94-02 JENDL-3.2.                                                  
      COMPILED BY T.NAKAGAWA (NDC/JAERI)                          
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (3,2), (3,4), (3,51-91), (3,16), (3,17), (3,22), (3,28)     
      (4,16-91)                                                   
      (5,16-91)                                                   
            THESE DATA WERE ADOPTED FROM JENDL FUSION FILE.       
      (12,102)                                                    
     ***********************************************************  
                                                                  
     -------------------------------------------------------------
      JENDL FUSION FILE /2/  (AS OF OCT. 1993)                    
        EVALUATED BY K.KOSAKO(NEDAC) AND S.CHIBA (NDC/JAERI)      
        COMPILED BY K.KOSAKO                                      
                                                                  
          THE INELASTIC SCATTERING, (N,2N), (N,3N), (N,NP), (N,NA)
        CROSS SECTIONS WERE CALCULATED WITH SINCROS-II SYSTEM/3/. 
        THE OTHER CROSS SECTIONS WERE TAKEN FROM JENDL-3.1.  MF=6 
        OF MT=16, 17, 22, 28 AND 91 WERE CREATED WITH F15TOB      
        PROGRAM /2/ IN WHICH KUMABE'S SYSTEMATICS /4/ WAS USED.   
        THE PRECOMPOUND/COMPOUND RATIO WAS CALCULATED BY THE      
        SINCROS-II CODE SYSTEM/3/.                                
          OPTICAL-MODEL, LEVEL DENSITY AND OTHER PARAMETERS USED  
        IN THE SINCROS-II CALCULATION ARE DESCRIBED IN REF./3/.   
        LEVEL SCHEMES WERE DETERMINED ON THE BASIS OF ENSDF/5/.   
     -------------------------------------------------------------
                                                                  
                                                                  
MF = 1  GENERAL INFORMATION                                       
  MT=451 COMMENTS AND DICTIONARY                                  
                                                                  
MF = 2  RESONANCE PARAMETERS                                      
  MT=151 RESOLVED AND UNRESOLVED RESONANCE PARAMETERS             
  RESOLVED RESONANCE REGION (MLBW FORMULA)                        
    EVALUATED BY KIKUCHI ET AL./6/ ON THE BASIS OF THE FOLLOWING  
    EXPERIMENTS.                                                  
     MO-92: BELOW 50 KEV                                          
       TRANSMISSION : WASSON ET AL./7/                            
       CAPTURE      : WASSON ET AL./7/, WEIGMANN ET AL./8/,       
                      MUSGROVE ET AL./9/                          
     MO-94: BELOW 20 KEV                                          
       CAPTURE      : WEIGMANN ET AL./8/, MUSGROVE ET AL./9/      
     MO-95: BELOW 2 KEV                                           
       TRANSMISSION : SHWE ET AL./10/                             
       CAPTURE      : WEIGMANN ET AL./8/                          
     MO-96: BELOW 19 KEV                                          
       CAPTURE      : WEIGMANN ET AL./8/, MUSGROVE ET AL./9/      
     MO-97: BELOW 1.8 KEV                                         
       TRANSMISSION : SHWE ET AL./10/                             
       CAPTURE      : WEIGMANN ET AL./8/                          
     MO-98: BELOW 32 KEV                                          
       TRANSMISSION : CHRIEN ET AL./11/                           
       CAPTURE      : WEIGMANN ET AL./8/, MUSGROVE ET AL./9/      
     MO-100: BELOW 26 KEV                                         
       TRANSMISSION : WEIGMANN ET AL./12/                         
       CAPTURE      : WEIGMANN ET AL./8/, MUSGROVE ET AL./9/      
    ASSUMED RADIATIVE WIDTHS(EV)                                  
                 S-WAVE    P-WAVE            S-WAVE    P-WAVE     
         MO-92   0.02      0.425      MO-94   0.135     0.175     
         MO-95   0.150     0.180      MO-96   0.114     0.136     
         MO-97   0.130     0.150      MO-98   0.085     0.12      
         MO-100  0.065     0.08                                   
  UNRESOLVED RESONANCE REGION : UP TO 100 KEV                     
    THE NEUTRON STRENGTH FUNCTIONS WERE CALCULATED WITH OPTICAL   
    MODEL CODE CASTHY/13/.  THE LEVEL SPACING WAS DETERMINED TO   
    REPRODUCE THE CAPTURE CROSS SECTION CALCULATED WITH CASTHY.   
    THE SCATTERING RADIUS WAS OBTAINED FROM FITTING TO THE        
    CALCULATED TOTAL CROSS SECTION AT 100 KEV.                    
                                                                  
  TYPICAL VALUES OF THE AVERAGE PARAMETERS AT 70 KEV:             
             S0        S1        S2       GG(EV)   DO(EV)  R(FM)  
    MO-92   0.369E-4  5.479E-4  0.364E-4  0.226    2252    6.746  
    MO-94   0.369E-4  5.479E-4  0.365E-4  0.230    1101    6.699  
    MO-95   0.369E-4  5.479E-4  0.365E-4  0.232    76.12   6.680  
    MO-96   0.370E-4  5.480E-4  0.365E-4  0.162    93.33   6.698  
    MO-97   0.370E-4  5.479E-4  0.365E-4  0.180    58.76   6.687  
    MO-98   0.370E-4  5.479E-4  0.364E-4  0.133    765.9   6.675  
    MO-100  0.370E-4  5.479E-4  0.365E-4  0.085    576.1   6.651  
                                                                  
  CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS)   
                     2200 M/S               RES. INTEG.           
      TOTAL           8.066                    -                  
      ELASTIC         5.483                    -                  
      CAPTURE         2.582                   25.68               
                                                                  
MF = 3  NEUTRON CROSS SECTIONS                                    
  BELOW 100 KEV, RESONANCE PARAMETERS WERE GIVEN.                 
                                                                  
  FOR JENDL-3.1, THE SPHERICAL OPTICAL AND STATISTICAL MODEL      
  CALCULATION WAS PERFORMED WITH CASTHY/13/ IN THE ENERGY RANGE   
  ABOVE 100 KEV, BY TAKING ACCOUNT OF COMPETING REACTIONS OF WHICH
  CROSS SECTIONS WERE CALCULATED WITH A PREEQUILIBRIUM AND        
  MULTI-STEP EVAPORATION MODEL CODE PEGASUS/14/.  THE OMP'S FOR   
  NEUTRON GIVEN IN TABLE 1 WERE DETERMINED BY IIJIMA ET AL./15/ TO
  REPRODUCE A SYSTEMATIC TREND OF THE TOTAL CROSS SECTION.  THE   
  OMP'S FOR CHARGED PARTICLES ARE AS FOLLOWS:                     
     PROTON   = PEREY/16/                                         
     ALPHA    = HUIZENGA AND IGO/17/                              
     DEUTERON = LOHR AND HAEBERLI/18/                             
     HELIUM-3 AND TRITON = BECCHETTI AND GREENLEES/19/            
  PARAMETERS FOR THE COMPOSITE LEVEL DENSITY FORMULA OF GIRBERT   
  AND CAMERON/20/ WERE EVALUATED BY IIJIMA ET AL./21/.  MORE      
  EXTENSIVE DETERMINATION AND MODIFICATION WERE MADE IN THE       
  PRESENT WORK.  TABLE 2 SHOWS THE LEVEL DENSITY PARAMETERS USED  
  IN THE PRESENT CALCULATION.  THE ENERGY DEPENDENCE OF SPIN      
  CUT-OFF PARAMETER IN THE ENERGY RANGE BELOW E-JOINT (EX) IS DUE 
  TO GRUPPELAAR/22/.                                              
                                                                  
  FOR JENDL-3.2, DATA OF NEUTRON EMITTING REACTIONS WERE ADOPTED  
  FROM JENDL FUSION FILE.  THE THORETICAL CALCULATION WAS MADE    
  WITH SINCROS-II SYSTEM/3/ BY ADOPTIG WALTER-GUSS OMP MODIFIED   
  BY YAMAMURO/3/ FOR NEUTRONS, LEMOS OMP MODIFIED BY ARTHUR AND   
  YOUNG/23/ FOR ALPHA, THE SAME OMP'S AS THE PEGASUS CALCULATION  
  FOR OTHER CHARGED PARTICLES AND STANDARD LEVEL DENSITY          
  PARAMETERS OF SINCROS-II SYSTEM.                                
                                                                  
  THE DATA FOR MT=1, 102, 103, 104, 105, 106, 107, 11 AND 251 ARE 
  THE SAME AS JENDL-3.1.                                          
                                                                  
  MT = 1  TOTAL                                                   
    BELOW 500 KEV, SPHERICAL OPTICAL MODEL CALCULATION WAS        
    ADOPTED. OMP IN TABLE 1 AND CASTHY WERE USED.  ABOVE 500 KEV, 
    SPLINE-FITTING TO THE DATA MEASURED BY FOSTER AND GLASGOW     
    /24/, LAMBROPOULOS ET AL./25/ AND POENITZ AND WHALEN/26/ WAS  
    MADE.                                                         
                                                                  
  MT = 2  ELASTIC SCATTERING                                      
    CALCULATED AS (TOTAL - SUM OF PARTIAL CROSS SECTIONS).        
                                                                  
  MT = 4, 51 - 91  INELASTIC SCATTERING                           
    TAKEN FROM JENDL FUSION FILE.  THE INELASTIC SCATTERING CROSS 
    SECTIONS FOR EACH ISOTOPE WERE GROUPED IN NATURAL MO DATA AS  
    FOLLOWS:                                                      
                                                                  
      MT -Q(MEV)   MO-92  MO-94  MO-95  MO-96  MO-97  MO-98 MO-100
      51  0.2041     -      -      51     -      -      -     -   
      52  0.4809     -      -      -      -      51     -     -   
      53  0.5356     -      -      -      -      -      -     51  
      54  0.6579     -      -      -      -    52,53    -     -   
      55  0.6944     -      -      -      -      -      -     52  
      56  0.7192     -      -      -      -    54,55    -     -   
      57  0.7348     -      -      -      -      -      51    -   
      58  0.7530     -      -      52     -      56     -     -   
      59  0.7820     -      -      53     51     57     52    -   
      60  0.8206     -      -      54     -      58     -     -   
      61  0.8711     -      51     -      -      59     -     -   
      62  0.9477     -      -      55     -      60     -     -   
      63  1.0245     -      -      56     -      61     -     -   
      64  1.0567     -      -    57,58    -      62     -     53  
      65  1.1168     -      -      -      52     63     -     54  
      66  1.3023     -      -    59,60    -      -      -     -   
      67  1.4257     -      -      61     -      -      53    -   
      68  1.4977     51     -      -      53     -      54    -   
      69  1.5408     -      52   62,63    -      -      -     -   
      70  1.6202     -      -    64,65  54,55    -      -     -   
      71  1.7425     -      53     -      -      -      55    -   
      72  1.8643     -      54     -      56     -      56    -   
      73  1.9650     -      -      -      57     -    57,58   -   
      74  2.0376     -      55     -      58     -    59,60   -   
      75  2.2063     -      -      -    59,60    -    61,62   -   
      76  2.2826     52     56     -      -      -    63,64   -   
      77  2.3932     -    57,58    -    61-63    -      -     -   
      78  2.4810     -      -      -      64     -      -     -   
      79  2.5015   53,54    -      -      65     -      -     -   
      80  2.5339     -    59,60    -      66     -      -     -   
      81  2.5943     55     61     -      67     -      -     -   
      82  2.7398     56   62,63    -      -      -      -     -   
      83  2.8058     57   64,65    -      -      -      -     -   
      84  2.8702     -    66,67    -      -      -      -     -   
      85  2.9558     58   68,69    -      -      -      -     -   
      86  3.0641   59,60    -      -      -      -      -     -   
      87  3.3691     61     -      -      -      -      -     -   
      88  3.5420   62,63    -      -      -      -      -     -   
      89  3.6212   64-66    -      -      -      -      -     -   
    OTHERS WERE SUMMED UP TO MT=91.                               
                                                                  
  MT = 16, 17, 22, 28   (N,2N), (N,3N), (N,NA) AND (N,NP)         
    ADOPTED FROM JENDL FUSION FILE.  NORMALIZATION OF THE RESULTS 
    WAS NOT MADE BECAUSE THE PARAMETERS USED WERE DETERMINED BY   
    YAMAMURO/27/ TO REPRODUCE WELL EXPERIMENTAL DATA.             
                                                                  
  MT = 102  CAPTURE                                               
    SPHERICAL OPTICAL AND STATISTICAL MODEL CALCULATION WITH      
    CASTHY/13/ WAS ADOPTED.  DIRECT AND SEMI-DIRECT CAPTURE CROSS 
    SECTIONS WERE ESTIMATED ACCORDING TO THE PROCEDURE OF BENZI   
    AND REFFO/28/ AND NORMALIZED TO 1 MILLI-BARN AT 14 MEV.       
    THE GAMMA-RAY STRENGTH FUNCTIONS WERE ADJUSTED TO REPRODUCE   
    THE CAPTURE CROSS SECTION MEASURED BY MUSGROVE ET AL./8/.     
       MO-92: 0.941E-4,  MO-94: 1.966E-4,  MO-95: 29.76E-4,       
       MO-96: 1.623E-4,  MO-97: 29.76E-4,  MO-98: 1.623E-4,       
       MO-100: 1.432E-4,                                          
                                                                  
  MT = 103,104,105,106,107,111                                    
       (N,P), (N,D), (N,T), (N,HE3), (N,ALPHA) AND (N,2P)         
    THESE REACTION CROSS SECTIONS WERE CALCULATED WITH PEGASUS    
    /14/.  THE KALBACH'S CONSTANTS WERE  ESTIMATED BY THE FORMULA 
    DERIVED FROM KIKUCHI-KAWAI'S FORMALISM/29/ AND LEVEL DENSITY  
    PARAMETERS.  THE (N,P) AND (N,ALPHA) CROSS SECTIONS WERE      
    NORMALIZED TO THE EXPERIMENTAL DATA OR SYSTEMATICS AT 14.5    
    MEV.  FOR MORE DETAILS, SEE COMMENT OF EACH ISOTOPE.          
                                                                  
  MT = 251  MU-BAR                                                
    CALCULATED WITH CASTHY/13/.                                   
                                                                  
MF = 4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS               
  MT = 2                                                          
    CALCULATED WITH CASTHY/13/ (SAME AS JENDL-3.1).               
  MT = 51-89                                                      
    TAKEN FROM JENDL FUSION FILE WHICH WAS CALCULATED WITH CASTHY 
    AND DWUCKY IN THE SINCROS-II SYSTEM.                          
  MT = 16,17,22,28,91                                             
    TRANSFORMED FROM MF=6 DATA (DDX) OF JENDL FUSION FILE.        
                                                                  
MF = 5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                
  MT = 16,17,22,28,91                                             
    TRANSFORMED FROM MF=6 DATA (DDX) OF JENDL FUSION FILE.        
                                                                  
MF =12  PHOTON PRODUCTION MULTIPLICITIES                          
  MT = 102 (BELOW 420 KEV)                                        
    DETERMINED FROM ENERGY BALANCE.                               
                                                                  
MF =13  PHOTON PRODUCTION CROSS SECTIONS                          
  MT = 3 (ABOVE 420 KEV)                                          
    FITTED WITH THE EMPIRICAL FORMULA BY HOWERTON AND PLECHATY    
    /30/ BASED ON THE EXPERIMENTAL DATA/31/.                      
                                                                  
MF =14  PHOTON ANGULAR DISTRIBUTIONS                              
  MT = 3,102                                                      
    ASSUMED TO BE ISOTROPIC.                                      
                                                                  
MF =15  CONTINUOUS PHOTON ENERGY SPECTRA                          
  MT = 3                                                          
    FITTED WITH THE EMPIRICAL FORMULA BY HOWERTON AND PLECHATY    
    /30/ BASED ON THE EXPERIMENTAL DATA/31/, AND COMPARED WITH    
    EXPERIMENTAL DATA MEASURED BY YAMAMURO ET AL./32/.            
  MT = 102                                                        
    CALCULATED WITH CASTHY/13/ FOR EACH ISOTOPE AND CONSTRUCTED   
    ACCORDING TO THEIR ABUNDANCES.                                
                                                                  
                                                                  
================================================================= 
  FOLLOWING ARE PARAMETERS USED IN THE CASTHY AND PEGASUS CALC.   
================================================================= 
                                                                  
TABLE 1  NEUTRON OPTICAL POTENTIAL PARAMETERS                     
                                                                  
                DEPTH (MEV)       RADIUS(FM)    DIFFUSENESS(FM)   
         ----------------------   ------------  ---------------   
        V  = 46.0-0.25E           R0 = 5.893    A0 = 0.62         
        WS = 7.0                  RS = 6.393    AS = 0.35         
        WSO= 7.0                  RSO= 5.893    ASO= 0.62         
                                                                  
TABLE 2  LEVEL DENSITY PARAMETERS                                 
                                                                  
 NUCL.    SYST A(/MEV)   T(MEV)    C(/MEV)   EX(MEV)   PAIRING    
 ---------------------------------------------------------------  
 40-ZR- 88  *  1.404E+01 7.386E-01 4.932E-01 7.870E+00 2.660E+00  
 40-ZR- 89     1.095E+01 8.260E-01 1.379E+00 5.864E+00 1.200E+00  
 40-ZR- 90     9.152E+00 8.222E-01 1.526E-01 5.383E+00 2.130E+00  
 40-ZR- 91     1.036E+01 8.000E-01 7.822E-01 5.057E+00 1.200E+00  
 40-ZR- 92     1.088E+01 8.192E-01 5.122E-01 6.429E+00 1.920E+00  
 40-ZR- 93     1.298E+01 7.000E-01 1.273E+00 5.183E+00 1.200E+00  
 40-ZR- 94     1.275E+01 7.530E-01 4.411E-01 7.019E+00 2.320E+00  
 40-ZR- 95     1.331E+01 6.070E-01 5.453E-01 3.985E+00 1.200E+00  
 40-ZR- 96     1.320E+01 7.000E-01 2.235E-01 6.589E+00 2.490E+00  
 40-ZR- 97     1.259E+01 5.590E-01 2.497E-01 3.084E+00 1.200E+00  
 40-ZR- 98  *  1.725E+01 6.633E-01 1.790E+00 7.555E+00 2.140E+00  
 40-ZR- 99  *  1.831E+01 6.566E-01 1.170E+01 6.957E+00 1.200E+00  
                                                                  
 41-NB- 89  *  1.420E+01 7.303E-01 2.467E+00 6.611E+00 1.460E+00  
 41-NB- 90  *  1.395E+01 7.222E-01 1.458E+01 4.869E+00 0.0        
 41-NB- 91  *  9.464E+00 7.143E-01 3.924E-01 3.082E+00 9.300E-01  
 41-NB- 92     1.040E+01 8.410E-01 4.607E+00 4.477E+00 0.0        
 41-NB- 93     1.250E+01 7.120E-01 2.205E+00 4.629E+00 7.200E-01  
 41-NB- 94     1.281E+01 7.230E-01 7.763E+00 4.250E+00 0.0        
 41-NB- 95     1.277E+01 7.500E-01 2.121E+00 5.782E+00 1.120E+00  
 41-NB- 96     1.331E+01 5.880E-01 3.406E+00 2.530E+00 0.0        
 41-NB- 97     1.337E+01 6.710E-01 9.771E-01 5.026E+00 1.290E+00  
 41-NB- 98     1.380E+01 5.110E-01 2.350E+00 1.731E+00 0.0        
 41-NB- 99  *  1.742E+01 6.566E-01 1.085E+01 6.300E+00 9.400E-01  
 41-NB-100  *  1.850E+01 6.500E-01 7.329E+01 5.699E+00 0.0        
                                                                  
 42-MO- 90  *  1.436E+01 7.222E-01 4.129E-01 7.834E+00 2.740E+00  
 42-MO- 91     1.168E+01 7.820E-01 1.284E+00 5.770E+00 1.280E+00  
 42-MO- 92     1.064E+01 7.770E-01 2.062E-01 5.938E+00 2.210E+00  
 42-MO- 93     1.125E+01 7.800E-01 9.792E-01 5.457E+00 1.280E+00  
 42-MO- 94     1.301E+01 6.850E-01 3.417E-01 5.770E+00 2.000E+00  
 42-MO- 95     1.360E+01 7.150E-01 1.847E+00 5.835E+00 1.280E+00  
 42-MO- 96     1.403E+01 7.410E-01 6.991E-01 7.645E+00 2.400E+00  
 42-MO- 97     1.517E+01 6.800E-01 2.769E+00 6.036E+00 1.280E+00  
 42-MO- 98     1.594E+01 6.900E-01 7.358E-01 7.888E+00 2.570E+00  
 42-MO- 99     1.774E+01 6.200E-01 4.294E+00 6.058E+00 1.280E+00  
 42-MO-100     1.780E+01 6.000E-01 6.702E-01 6.645E+00 2.220E+00  
 42-MO-101     2.085E+01 5.650E-01 7.153E+00 6.092E+00 1.280E+00  
 ---------------------------------------------------------------  
  SYST:  * = LDP'S WERE DETERMINED FROM SYSTEMATICS.              
  SPIN CUT-OFF PARAMS WERE CALCULATED AS 0.146*SQRT(A)*A**(2/3).  
                                                                  
REFERENCES                                                        
 1) KAWAI, M. ET AL.: J. NUCL. SCI. TECHNOL., 29, 195 (1992).     
 2) CHIBA, S. ET AL.: JAERI-M 92-027, P.35 (1992).                
 3) YAMAMURO, N.: JAERI-M 90-006 (1990).                          
 4) KUMABE, I. ET AL.: NUCL. SCI. ENG., 104, 280 (1990).          
 5) ENSDF: EVALUATED NUCLEAR STRUCTURE DATA FILE, BNL/NNDC.       
 6) KIKUCHI, Y. ET AL.: JAERI-M 86-030 (1986).                    
 7) WASSON, O.A. ET AL.: PHYS. REV., C7, 1532 (1973).             
 8) WEIGMANN, H. ET AL.: 1971 KONOXVILLE, 749 (1971).             
 9) MUSGROVE, A.R.DE L. ET AL.: NUCL. PHYS., A270, 108 (1976).    
10) SHWE H. AND COTE R.E.: PHYS. REV. 179, 1148 (1969).           
11) CHRIEN, R.E. ET AL.: PHYS. REV., C13, 578 (1976).             
12) WEIGMANN, H. ET AL.: PHYS. REV., C20, 115 (1969).             
13) IGARASI, S. AND FUKAHORI, T.: JAERI 1321 (1991).              
14) IIJIMA, S. ET AL.: JAERI-M 87-025, P. 337 (1987).             
15) IIJIMA, S. AND KAWAI, M.: J. NUCL. SCI. TECHNOL. 20, 77(1983).
16) PEREY, F.G: PHYS. REV. 131, 745 (1963).                       
17) HUIZENGA, J.R. AND IGO, G.: NUCL. PHYS. 29, 462 (1962).       
18) LOHR, J.M. AND HAEBERLI, W.: NUCL. PHYS. A232, 381 (1974).    
19) BECCHETTI, F.D., JR. AND GREENLEES, G.W.: POLARIZATION        
    PHENOMENA IN NUCLEAR REACTIONS, P. 682, THE UNIVERSITY OF     
    WISCONSIN PRESS.  (1971).                                     
20) GILBERT, A. AND CAMERON, A.G.W.: CAN. J. PHYS., 43,1446(1965).
21) IIJIMA, S., ET AL.: J. NUCL. SCI. TECHNOL. 21, 10 (1984).     
22) GRUPPELAAR, H.: ECN-13 (1977).                                
23) ARTHUR, E.D. AND YOUNG, P.G.: LA-8626-MS (1980).              
24) FOSTER JR.D.G. AND GLASGOW D.W.: PHYS. REV., C3, 576 (1971).  
25) LAMBROPOULOS, P. ET AL.: NUCL. PHYS., A201, 1 (1973).         
26) POENITZ, W.P. AND WHALEN, J.F.; ANL/NDM-80 (1983).            
27) YAMAMURO, N.: NUCL. SCI. ENG., 109, 128 (1991).               
28) BENZI, V. AND REFFO, G.: CCDN-NW/10 (1969).                   
29) KIKUCHI, K. AND KAWAI, M.: "NUCLEAR MATTER AND NUCLEAR        
    REACTIONS", NORTH HOLLAND (1968).                             
30) HOWERTON, S.T. AND PLECHATY, E.F.: NUCL. SCI. ENG., 32, 178   
   (1968).                                                        
31) MORGAN, G. AND NEWMAN, N.: ORNL-TM-5097 (1975).               
32) YAMAMURO, N. ET AL.: 1982 ANTWERP, 152 (1982).