94-Pu-240

 94-PU-240 NAIG+      EVAL-MAY87 T.MURATA, A.ZUKERAN              
                      DIST-SEP89 REV2-AUG93                       
----JENDL-3.2         MATERIAL 9440                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
87-05 EVALUATION WAS MADE BY                                      
        T.MURATA (NAIG)   : CROSS SECTIONS ABOVE RESONANCE REGION 
                    AND OTHER QUANTITIES,                         
        A.ZUKERAN(HITACHI): RESONANCE PARAMETERS.                 
88-06 MT'S=16, 17, 37 AND 102 WERE MODIFIED.                      
89-02 FP YIELDS WERE TAKEN FROM JNDC FP DECAY FILE VERSION-2.     
        COMPILATION WAS MADE BY T. NAKAGAWA (JAERI).              
90-07 FP YIELD DATA WERE MODIFIED.                                
90-10 MF=5, MT=16, 17, 91: MODIFIED AT THRESHOLD ENERGIES.        
93-08 JENDL-3.2.                                                  
      COMPILED BY T.NAKAGAWA (NDC/JAERI)                          
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (1,452), (1,455)                                            
     ***********************************************************  
                                                                  
                                                                  
MF=1  GENERAL INFORMATION                                         
  MT=451  COMMENTS AND DICTIONARY                                 
  MT=452  NUMBER OF NEUTRONS PER FISSION                          
      SUM OF MT=455(DELAYED NEUTRONS) AND MT=456(PROMPT NEUTRONS).
  MT=455  DELAYED NEUTRON DATA                                    
      BELOW 5 MEV, NU-D OF 0.00911 MEASURED BY BENEDETTI ET AL.   
      /1/ WAS ADOPTED.  ABOVE 6 MEV, 0.0067 WAS GIVEN ON THE BASIS
      OF TUTTLE'S SYSTEMATICS /2/.  DECAY CONSTANTS WERE TAKEN    
      FROM EVALUATION BY BARDY AND ENGLAND /3/.                   
  MT=456  NUMBER OF PROMPT NEUTRONS                               
      LINEAR LEAST-SQUARES FITTING TO THE EXPERIMENTAL DATA OF    
      FREHAUT ET AL. /4/ RENORMALIZED TO CF-252 NU-P=3.756.       
                                                                  
MF=2  RESONANCE PARAMETERS                                        
  MT=151  RESOLVED AND UNRESOLVED RESONANCE PARAMETERS            
  1) RESOLVED RESONANCES FOR MLBW FORMULA (1.0E-5 TO 4 KEV)       
      PARAMETERS OF A NEGATIVE AND THE 1.057-EV RESONANCES WERE   
      REVISED ON THE BASIS OF RECOMMENDATION BY MUGHABGHAB /5/.   
      NEUTRON AND CAPTURE WIDTHS OF OTHER LEVELS WERE BASED ON THE
      EXPERIMENTAL DATA BY HOCKENBURY ET AL. /6/ IN THE ENERGY    
      RANGE FROM 20 TO 500 EV, AND KOLAR AND BOECKHOFF /7/ FROM   
      500 EV TO 4 KEV.  THE AVERAGE CAPTURE WIDTH OF 29.5 MILLI-EV
      WAS ASSUMED FOR THE RESONANCES WHOSE CAPTURE WIDTHS WERE    
      UNKNOWN.  BELOW 610 EV, THE SUB-THRESHOLD FISSION WIDTHS    
      WERE CALCULATED FROM THE AREA DATA BY WESTON AND TODD /8/.  
      ABOVE 610 EV, THEY WERE TAKEN FROM THE DATA BY AUCHAMPAUGH  
      AND WESTON /9/.                                             
  2) UNRESOLVED RESONANCES (4 TO 40 KEV)                          
      ENERGY DEPENDENT PARAMETERS WERE DETERMINED TO REPRODUCE THE
      EVALUATED CROSS SECTIONS IN THIS ENERGY REGION.  FISSION    
      WIDTHS WERE ADJUSTED TO AVERAGE CROSS SECTIONS MEASURED BY  
      WESTON AND TODD /8/.                                        
                                                                  
      CALCULATED 2200-M/SEC CROSS SECTIONS AND RES. INTEGERALS.   
                     2200-M/SEC     RES. INTEG.                   
          TOTAL      291.13   B                                   
          ELASTIC      1.644  B        -                          
          FISSION      0.0588 B        8.94 B                     
          CAPTURE    289.4    B     8110.   B                     
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  BELOW 4 KEV: BACKGROUND CROSS SECTIONS ARE GIVEN TO THE CAPTURE 
               CROSS SECTION.                                     
  ABOVE 4 KEV: EVALUATED AS FOLLOWS.  IN THE ENERGY RANGE FROM 4  
               TO 40 KEV, THE CROSS SECTIONS ARE REPRESENTED WITH 
               THE UNRESOLVED RESONANCE PARAMETERS, AND THE BACK- 
               GROUND CROSS SECTIONS ARE GIVEN IN MF=3.           
  MT=1    TOTAL                                                   
      EVALUATED WITH SPLINE FITTING TO THE EXPERIMENTAL DATA OF   
      SMITH ET AL./10/, KAEPPELER ET AL./11/ AND POENITZ ET       
      AL./12/                                                     
                                                                  
  MT=2    ELASTIC SCATTERING                                      
      OBTAINED BY SUBTRACTING THE OTHER CROSS SECTIONS FROM TOTAL 
      CROSS SECTION.                                              
                                                                  
  MT=4    TOTAL INELASTIC SCATTERING                              
      SUM OF PARTIAL INELASTIC SCATTERING CROSS SECTIONS (MT=51   
      TO MT=91).                                                  
                                                                  
  MT=51-78, 91  PARTIAL INELASTIC SCATTERING                      
      BELOW 3 MEV, THE RESULTS OF STATISTICAL AND COUPLED-CHANNEL 
      CALCULATION MADE BY LAGRANGE ET AL. /13/ WERE ADOPTED.  FOR 
      SOME LEVELS, FOR WHICH SMITH'S EXPERIMENTAL DATA /14/ WERE  
      AVAILABLE, THE CALCULATED RESULTS WERE NORMALIZED (FOR 1ST, 
      2ND, 3RD, 5TH AND 9 TO 11TH LEVELS).                        
                                                                  
      LEVEL SCHEME                                                
                NO.      ENERGY(MEV)   SPIN-PARITY                
                G.S.       0.0            0 +                     
                 1         0.04285        2 +                     
                 2         0.14169        4 +                     
                 3         0.29431        6 +                     
                 4         0.4976         8 +                     
                 5         0.59736        1 -                     
                 6         0.64889        3 -                     
                 7         0.74232        5 -                     
                 8         0.8607         0 +                     
                 9         0.90032        2 +                     
                10         0.93807        1 -                     
                11         0.95887        2 -                     
                12         0.9924         4 +                     
                13         1.0018         3 -                     
                14         1.0306         3 +                     
                15         1.0375         4 -                     
                16         1.0764         4 +                     
                17         1.0895         0 +                     
                18         1.1155         5 -                     
                19         1.1370         2 +                     
                20         1.1615         6 -                     
                21         1.1778         3 +                     
                22         1.2230         2 +                     
                23         1.2325         4 +                     
                24         1.2408         2 -                     
                25         1.2621         3 +                     
                26         1.2820         3 -                     
                27         1.30873        5 -                     
                28         1.41079        0 +                     
            LEVELS ABOVE 1.4108 MEV WERE ASSUMED TO BE CONTINUUM. 
                                                                  
  MT=16,17,37  (N,2N),(N,3N) AND (N,4N)                           
      CALCULATED FROM NEUTRON EMISSION CROSS SECTION AND BRANCHING
      RATIO TO EACH REACTION CHANNEL.  NEUTRON EMISSION CROSS     
      SECTION WAS OBTAINED BY SUBTRACTING THE FISSION AND CAPTURE 
      CROSS SECTIONS FROM COMPOUND NUCLEUS FORMATION CROSS SECTION
      CALCULATED WITH SPHERICAL OPTICAL MODEL.  BRANCHING RATIO   
      WAS OBTAINED FROM FORMALISM GIVEN BY SEGEV ET AL. /15/      
                                                                  
  MT=18   FISSION                                                 
    BELOW 100 KEV: AVERAGE VALUES OF FISSION CROSS SECTION        
      MEASURED BY WESTON AND TODD /8/ WERE NORMALIZED TO THE      
      VALUE AT 100 KEV OF THE SIMULTANEOUS EVALUATION.            
    ABOVE 100 KEV: SIMULTANEOUS EVALUATION WAS MADE BY TAKING     
      ACCOUNT OF EXPERIMENTAL DATA OF FISSION RATIO AND ABSOLUTE  
      CROSS SECTIONS OF U-235, U-238, PU-239, PU-240 AND PU-241,  
      AND CAPTURE CROSS SECTION OF AU-197 /16/.                   
                                                                  
  MT=102  CAPTURE                                                 
    BELOW 350 KEV: BASED ON THE EXPERIMENTAL DATA OF HOCKENBURY ET
      AL. /6/, WESTON AND TODD /17/ AND THE RATIO DATA OF WISSHAK 
      AND KAEPPELER /18/ WITH THE CAPTURE CROSS SECTION OF AU-197 
      /16/.  AS A GUIDE LINE, STATISTICAL MODEL CALCULATION WAS   
      MADE WITH CASTHY CODE /19/.                                 
    ABOVE 350 KEV: THE STATISTICAL MODEL CALCULATION WAS          
      NORMALIZED TO THE VALUE AT 350 KEV.  DIRECT AND COLLECTIVE  
      CAPTURE WAS INCLUDED IN HIGH ENERGY REGION ADOPTING THE     
      VALUE FOR U-238 GIVEN BY KITAZAWA ET AL. /20/.              
                                                                  
      THE SPHERICAL OPTICAL POTENTIAL PARAMETERS                  
         V  = 40.6 - 0.05*EN,  WS = 6.5 + 0.15*EN (MEV)           
         VSO= 7.0                                 (MEV)           
         R  = RSO =1.32     ,  RS = 1.38          (FM)            
         A  = AS  = ASO =0.47                     (FM)            
      LEVEL DENSITY PARAMETERS WERE DETERMINED TO REPRODUCE THE   
      RESONANCE LEVEL SPACINGS AND STAIRCASES OF DISCRETE LEVELS. 
                                                                  
  MT=251  MU-BAR                                                  
      THE SAME AS JENDL-1 /21/ EXCEPT FOR 20 MEV.                 
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2                                                            
      TAKEN FROM JENDL-1 /21/.                                    
  MT=16,17,18,37,91                                               
      ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM.           
  MT=51-78                                                        
      FOR THE 1ST AND 2ND LEVELS, RESULTS OF LAGRANGE ET AL. /13/ 
      WERE ADOPTED.  FOR OTHERS, STATISTICAL AND DWBA CALCULATIONS
      WERE MADE.                                                  
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
  MT=16,17,91                                                     
      CALCULATED WITH  PRE-COMPOUND AND MULTI-STEP EVAPORATION    
      THEORY CODE PEGASUS /22/.                                   
  MT=37                                                           
      EVAPORATION SPECTRUM WAS GIVEN.                             
  MT=18  FISSION SPECTRA                                          
      CALCULATED FROM MADLAND-NIX FORMULA /23/.                   
         AVERAGE ENERGY RELEASE                   = 199.179 MEV   
         TOTAL AVERAGE FF KINETIC ENERGY          = 177.53 MEV    
         AVERAGE MASS NUMBER OF LIGHT FF          = 101           
         AVERAGE MASS NUMBER OF HEAVY FF          = 140           
         LEVEL DENSITY PARAMETER                  = A/10.0        
  MT=455  DELAYED NEUTRON SPECTRA                                 
      ASSUMED TO BE THE SAME AS PU-239 WHICH WERE TAKEN FROM THE  
      EVALUATION BY SAPHIER ET AL. /24/.                          
                                                                  
REFERENCES                                                        
 1) BENEDETTI G., ET AL.: NUCL. SCI. ENG., 80, 379 (1982).        
 2) TUTTLE R.J.: INDC(NDS)-107/G-SPECIAL, P.29 (1979).            
 3) BRADY M.C. AND ENGLAND T.R.: NUCL. SCI. ENG., 103, 129(1989). 
 4) FREHAUT J., ET AL.: CEA(R) 4626 (1974).                       
 5) MUGHABGHAB S.F.: "NEUTRON CROSS SECTIONS, VOL. 1, PART B",    
    ACADEMIC PRESS (1984).                                        
 6) HOCKENBURY R.W. ET AL.: NUCL. SCI. ENG., 49, 153 (1972).      
 7) KOLAR W. AND BOECKHOFF K.H.: J. NUCL. ENERGY, 22, 299 (1968). 
 8) WESTON L.W. AND TODD J.H.: NUCL. SCI. ENG., 88, 567 (1984).   
 9) AUCHAMPAUGH G.F. AND WESTON L.E.: PHYS. REV., C12, 1850       
    (1975).                                                       
10) SMITH A.B. ET AL.: NUCL. SCI. ENG., 47, 19 (1972).            
11) KAEPPLER F., ET AL.: PROC. OF MEETING ON NUCLEAR DATA OF      
    HIGHER PU AND AM ISOTOPES FOR REACTOR APPLICATION, HELD AT    
    BNL, P.49 (1978)                                              
12) POENITZ W.P., ET AL.; NUCL. SCI. ENG., 78, 333 (1981), AND    
    ANL/NDM-80 (1983).                                            
13) LAGRANGE CH. AND JARY J.: NEANDC(E) 198"L" (1978).            
14) SMITH A.B., ET AL.: IAEA-153, P.447 (1973).                   
15) SEGEV M., ET AL.: ANNALS OF NUCL. ENERGY, 5, 239 (1978).      
16) KANDA Y. ET AL.: 1985 SANTA FE, 2, 1567 (1986).               
17) WESTON L.W. AND TODD J.H.: NUCL. SCI. ENG.,63, 143 (1977).    
18) WISSHAK K. AND KAEPPELER F.: NUCL. SCI. ENG., 66, 363 (1978)  
    AND NUCL. SCI. ENG., 69, 39 (1979).                           
19) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                
20) KITAZAWA H., ET AL.: NUCL. PHYS., A307, 1 (1978).             
21) IGARASI S., ET AL.: JAERI 1261 (1979).                        
22) IIJIMA S., ET AL.: JAERI-M 87-025, P.337 (1987).              
23) MADLAND D.G. AND NIX J.R.: NUCL. SCI. ENG., 81, 213 (1982).   
24) SAPHIER D., ET AL.: NUCL. SCI. ENG., 62, 660 (1977).