46-Pd-107

 46-PD-107 JNDC       EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.        
                      DIST-SEP90 REV2-MAR93                       
----JENDL-3.2         MATERIAL 4640                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
84-10 EVALUATION FOR JENDL-2 WAS MADE BY JNDC FPND W.G./1/        
90-03 MODIFICATION FOR JENDL-3 WAS MADE/2/.                       
93-03 JENDL-3.2 WAS MADE BY JNDC FPND W.G.                        
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (2,151)       THE UPPER BOUNDARY OF RESOLVED RESONANCE      
                    REGION WAS CHANGED FROM 3.525 KEV TO 1 KEV    
     ***********************************************************  
                                                                  
                                                                  
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) : BELOW 1.0 KEV        
    RESONANCE PARAMETERS OF JENDL-2 WERE REEVALUATED AS FOLLOWS:  
       FOR JENDL-2, RESONANCE ENERGIES WERE BASED ON THE DATA BY  
    MACKLIN/3/.  NEUTRON WIDTHS WERE TAKEN FROM EXPERIMENTAL DATA 
    OF SINGH ET AL./4/ AND MACKLIN/3/.  THE AVERAGE RADIATION     
    WIDTH OF 0.125 EV/4/ WAS ASSUMED.                             
       FOR JENDL-3, THE RESONANCE ENERGIES WERE ADOPTED FROM      
    JENDL-2.  NEUTRON WIDTHS WERE TAKEN FROM THE MEASUREMENT OF   
    ANUFRIEV ET AL./5/ OR DETERMINED FROM THE CAPTURE AREA DATA   
    MEASURED BY MACKLIN/6/ AND AN AVERAGED RADIATION WIDTH OF     
    131+-69 MEV.  RADIATION WIDTHS OF RESONANCES WHOSE NEUTRON    
    WIDTH WAS MEASURED BY ANUFRIEV ET AL./5/ WERE DETERMINED      
    FROM THE DATA OF THE CAPTURE AREA MEASURED BY MACKLIN/6/ AND  
    THE NEUTRON WIDTH/5/.  TOTAL SPIN J OF SOME RESONANCES WAS    
    TENTATIVELY ESTIMATED WITH A RANDOM NUMBER METHOD.  NEUTRON   
    ORBITAL ANGULAR MOMENTUM L OF SOME RESONANCES WAS ESTIMATED   
    WITH A METHOD OF BOLLINGER AND THOMAS/7/.                     
                                                                  
  UNRESOLVED RESONANCE REGION : 1.000 KEV - 100 KEV               
    THE NEUTRON STRENGTH FUNCTIONS, S0, S1 AND S2 WERE CALCULATED 
    WITH OPTICAL MODEL CODE CASTHY/8/.  THE OBSERVED LEVEL SPACING
    WAS DETERMINED TO REPRODUCE THE CAPTURE CROSS SECTION         
    CALCULATED WITH CASTHY.  THE EFFECTIVE SCATTERING RADIUS WAS  
    OBTAINED FROM FITTING TO THE CALCULATED TOTAL CROSS SECTION AT
    100 KEV.  THE RADIATION WIDTH GG WAS BASED ON THE SYSTEMATICS 
    OF MEASURED VALUES FOR NEIGHBORING NUCLIDES.                  
                                                                  
  TYPICAL VALUES OF THE PARAMETERS AT 70 KEV:                     
    S0 = 0.810E-4, S1 = 3.030E-4, S2 = 0.960E-4, SG = 220.E-4,    
    GG = 0.125 EV, R  = 6.025 FM.                                 
                                                                  
  CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS)   
                     2200 M/S               RES. INTEG.           
      TOTAL           5.326                    -                  
      ELASTIC         3.318                    -                  
      CAPTURE         2.008                   112                 
                                                                  
MF = 3  NEUTRON CROSS SECTIONS                                    
  BELOW 100 KEV, RESONANCE PARAMETERS WERE GIVEN.                 
  ABOVE 100 KEV, THE SPHERICAL OPTICAL AND STATISTICAL MODEL      
  CALCULATION WAS PERFORMED WITH CASTHY, BY TAKING ACCOUNT OF     
  COMPETING REACTIONS, OF WHICH CROSS SECTIONS WERE CALCULATED    
  WITH PEGASUS/9/ STANDING ON A PREEQUILIBRIUM AND MULTI-STEP     
  EVAPORATION MODEL.  THE OMP'S FOR NEUTRON GIVEN IN TABLE 1 WERE 
  DETERMINED TO REPRODUCE THE CD-NATURAL TOTAL CROSS SECTIONS     
  MEASURED BY FOSTER AND GLASGOW/10/, POENITZ AND WHALEN/11/ AND  
  SO ON, AND APPLIED TO PD ISOTOPES.  THE OMP'S FOR CHARGED       
  PARTICLES ARE AS FOLLOWS:                                       
     PROTON   = PEREY/12/                                         
     ALPHA    = HUIZENGA AND IGO/13/                              
     DEUTERON = LOHR AND HAEBERLI/14/                             
     HELIUM-3 AND TRITON = BECCHETTI AND GREENLEES/15/            
  PARAMETERS FOR THE COMPOSITE LEVEL DENSITY FORMULA OF GILBERT   
  AND CAMERON/16/ WERE EVALUATED BY IIJIMA ET AL./17/  MORE       
  EXTENSIVE DETERMINATION AND MODIFICATION WERE MADE IN THE       
  PRESENT WORK.  TABLE 2 SHOWS THE LEVEL DENSITY PARAMETERS USED  
  IN THE PRESENT CALCULATION.  ENERGY DEPENDENCE OF SPIN CUT-OFF  
  PARAMETER IN THE ENERGY RANGE BELOW E-JOINT IS DUE TO GRUPPELAAR
  /18/.                                                           
                                                                  
  MT = 1  TOTAL                                                   
    SPHERICAL OPTICAL MODEL CALCULATION WAS ADOPTED.              
                                                                  
  MT = 2  ELASTIC SCATTERING                                      
    CALCULATED AS (TOTAL - SUM OF PARTIAL CROSS SECTIONS).        
                                                                  
  MT = 4, 51 - 91  INELASTIC SCATTERING                           
    SPHERICAL OPTICAL AND STATISTICAL MODEL CALCULATION WAS       
    ADOPTED.  THE LEVEL SCHEME WAS TAKEN FROM REF./19/.           
                                                                  
           NO.      ENERGY(MEV)    SPIN-PARITY                    
           GR.       0.0            5/2 +                         
            1        0.1157         1/2 +                         
            2        0.2140        11/2 -                         
            3        0.3028         5/2 +                         
            4        0.3122         7/2 +                         
            5        0.3482         1/2 +                         
            6        0.3660         9/2 +                         
            7        0.3819         3/2 +                         
            8        0.3924         7/2 +                         
            9        0.4120         1/2 +                         
           10        0.4712         3/2 +                         
           11        0.5677         5/2 +                         
           12        0.6701         5/2 +                         
           13        0.6850         7/2 -                         
           14        0.6980         1/2 +                         
           15        0.7590         3/2 +                         
           16        0.7810         3/2 -                         
           17        0.8060         3/2 -                         
           18        0.8090         5/2 +                         
           19        0.8890         1/2 +                         
           20        1.0230         3/2 +                         
      LEVELS ABOVE 1.03 MEV WERE ASSUMED TO BE OVERLAPPING.       
                                                                  
  MT = 102  CAPTURE                                               
    SPHERICAL OPTICAL AND STATISTICAL MODEL CALCULATION WITH      
    CASTHY WAS ADOPTED.  DIRECT AND SEMI-DIRECT CAPTURE CROSS     
    SECTIONS WERE ESTIMATED ACCORDING TO THE PROCEDURE OF BENZI   
    AND REFFO/20/ AND NORMALIZED TO 1 MILLI-BARN AT 14 MEV.       
                                                                  
    THE GAMMA-RAY STRENGTH FUNCTION (2.17E-02) WAS ADJUSTED TO    
    REPRODUCE THE CAPTURE CROSS SECTION OF 750 MILLI-BARNS AT 100 
    KEV MEASURED BY MACKLIN ET AL./21/                            
                                                                  
  MT = 16  (N,2N) CROSS SECTION                                   
  MT = 17  (N,3N) CROSS SECTION                                   
  MT = 22  (N,N'A) CROSS SECTION                                  
  MT = 28  (N,N'P) CROSS SECTION                                  
  MT = 32  (N,N'D) CROSS SECTION                                  
  MT =103  (N,P) CROSS SECTION                                    
  MT =104  (N,D) CROSS SECTION                                    
  MT =105  (N,T) CROSS SECTION                                    
  MT =107  (N,ALPHA) CROSS SECTION                                
    THESE REACTION CROSS SECTIONS WERE CALCULATED WITH THE        
    PREEQUILIBRIUM AND MULTI-STEP EVAPORATION MODEL CODE PEGASUS. 
                                                                  
    THE KALBACH'S CONSTANT K (=  97.8) WAS ESTIMATED BY THE       
    FORMULA DERIVED FROM KIKUCHI-KAWAI'S FORMALISM/22/ AND LEVEL  
    DENSITY PARAMETERS.                                           
                                                                  
    FINALLY, THE (N,P) AND (N,ALPHA) CROSS SECTIONS WERE          
    NORMALIZED TO THE FOLLOWING VALUES AT 14.5 MEV:               
      (N,P)         15.90  MB (SYSTEMATICS OF FORREST/23/)        
      (N,ALPHA)      3.64  MB (SYSTEMATICS OF FORREST)            
                                                                  
  MT = 251  MU-BAR                                                
    CALCULATED WITH CASTHY.                                       
                                                                  
MF = 4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS               
  LEGENDRE POLYNOMIAL COEFFICIENTS FOR ANGULAR DISTRIBUTIONS ARE  
  GIVEN IN THE CENTER-OF-MASS SYSTEM FOR MT=2 AND DISCRETE INELAS-
  TIC LEVELS, AND IN THE LABORATORY SYSTEM FOR MT=91.  THEY WERE  
  CALCULATED WITH CASTHY.  FOR OTHER REACTIONS, ISOTROPIC DISTRI- 
  BUTIONS IN THE LABORATORY SYSTEM WERE ASSUMED.                  
                                                                  
MF = 5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                
  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS WERE CALCULATED WITH 
  PEGASUS FOR INELASTIC SCATTERING FROM OVERLAPPING LEVELS AND FOR
  OTHER NEUTRON EMITTING REACTIONS.                               
                                                                  
TABLE 1  NEUTRON OPTICAL POTENTIAL PARAMETERS                     
                                                                  
                DEPTH (MEV)       RADIUS(FM)    DIFFUSENESS(FM)   
         ----------------------   ------------  ---------------   
        V  = 50.01-0.5528E        R0 = 5.972    A0 = 0.56         
        WS = 8.165                RS = 6.594    AS = 0.44         
        VSO= 5.261                RSO= 5.97     ASO= 0.267        
  THE FORM OF SURFACE ABSORPTION PART IS DER. WOODS-SAXON TYPE.   
                                                                  
TABLE 2  LEVEL DENSITY PARAMETERS                                 
                                                                  
 NUCLIDE  SYST A(1/MEV)  T(MEV)    C(1/MEV)  EX(MEV)   PAIRING    
 ---------------------------------------------------------------  
 44-RU-103     1.890E+01 6.480E-01 1.210E+01 7.110E+00 1.280E+00  
 44-RU-104     1.650E+01 6.780E-01 8.593E-01 7.878E+00 2.520E+00  
 44-RU-105     2.025E+01 6.060E-01 1.144E+01 6.747E+00 1.280E+00  
 44-RU-106     1.870E+01 6.300E-01 1.097E+00 7.896E+00 2.530E+00  
                                                                  
 45-RH-104     1.714E+01 5.910E-01 1.771E+01 4.018E+00 0.0        
 45-RH-105     1.637E+01 7.110E-01 8.434E+00 7.191E+00 1.240E+00  
 45-RH-106     1.700E+01 5.300E-01 8.449E+00 2.973E+00 0.0        
 45-RH-107     1.963E+01 5.480E-01 3.151E+00 5.336E+00 1.250E+00  
                                                                  
 46-PD-105     1.791E+01 6.700E-01 9.137E+00 7.207E+00 1.350E+00  
 46-PD-106     1.717E+01 6.660E-01 8.922E-01 8.024E+00 2.590E+00  
 46-PD-107     1.916E+01 6.110E-01 6.467E+00 6.507E+00 1.350E+00  
 46-PD-108     1.790E+01 6.460E-01 8.844E-01 7.957E+00 2.600E+00  
 ---------------------------------------------------------------  
  SYST:  * = LDP'S WERE DETERMINED FROM SYSTEMATICS.              
                                                                  
 SPIN CUTOFF PARAMETERS WERE CALCULATED AS 0.146*SQRT(A)*A**(2/3).
 IN THE CASTHY CALCULATION, SPIN CUTOFF FACTORS AT 0 MEV WERE     
 ASSUMED TO BE 4.350 FOR PD-107 AND 5.875 FOR PD-108.             
                                                                  
REFERENCES                                                        
 1) AOKI, T. ET AL.: PROC. INT. CONF. ON NUCLEAR DATA FOR BASIC   
    AND APPLIED SCIENCE, SANTA FE., VOL. 2, P.1627 (1985).        
 2) KAWAI, M. ET AL.: J. NUCL. SCI. TECHNOL., 29, 195 (1992).     
 3) MACKLIN, R.L.: PRIVATE COMMUNICATION (1984).                  
 4) SINGH, U.N., ET AL.: NUCL. SCI. ENG., 67, 54 (1978).          
 5) ANUFRIEV, V.A. ET AL.: PROC FIFTH ALL UNION CONF ON NEUTRON   
     PHYSICS, KIEV, SEPT. 1980, VOL. 2, 159 (1980).               
 6) MACKLIN, R.L. : NUCL. SCI. ENG., 89, 79 (1985).               
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10) FOSTER, D.G. JR. AND GLASGOW, D. W.: PHYS. REV., C3, 576      
    (1971).                                                       
11) POENITZ, W.P. AND WHALEN, J.F.: ANL-NDM-80 (1983).            
12) PEREY, F.G: PHYS. REV. 131, 745 (1963).                       
13) HUIZENGA, J.R. AND IGO, G.: NUCL. PHYS. 29, 462 (1962).       
14) LOHR, J.M. AND HAEBERLI, W.: NUCL. PHYS. A232, 381 (1974).    
15) BECCHETTI, F.D., JR. AND GREENLEES, G.W.: POLARIZATION        
    PHENOMENA IN NUCLEAR REACTIONS ((EDS) H.H. BARSHALL AND       
    W. HAEBERLI), P. 682, THE UNIVERSITY OF WISCONSIN PRESS.      
    (1971).                                                       
16) GILBERT, A. AND CAMERON, A.G.W.: CAN. J. PHYS., 43, 1446      
    (1965).                                                       
17) IIJIMA, S., ET AL.: J. NUCL. SCI. TECHNOL. 21, 10 (1984).     
18) GRUPPELAAR, H.: ECN-13 (1977).                                
19) MATSUMOTO, J., ET AL.: JAERI-M 7734 (1978).                   
20) BENZI, V. AND REFFO, G.: CCDN-NW/10 (1969).                   
21) MACKLIN, R.L., ET AL.: PROC. SPECIALISTS' MEETING ON NEUTRON  
    CROSS SECTIONS OF FISSION PRODUCTS, BOLOGNA 1979, NEANDC(E)   
    209L, 103.                                                    
22) KIKUCHI, K. AND KAWAI, M.: "NUCLEAR MATTER AND NUCLEAR        
    REACTIONS", NORTH HOLLAND (1968).                             
23) FORREST, R.A.: AERE-R 12419 (1986).