94-Pu-238

 95-Pu-238 MINSK BYEL EVAL-MAY97 V.M.Maslov et al.                
INDC(BLR)-009/G       DIST-MAR02 REV3-APR00            20000420   
----JENDL-3.3         MATERIAL 9434                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
79-03 New evaluation was made by T.Kawakita (PNC).                
89-03 Re-evaluation was made by T.Kawakita (MAPI) and             
      T.Nakagawa (JAERI).                                         
94-06 JENDL-3.2                                                   
      Nu-p, nu-d and nu-total were modified.                      
      Compiled by T.Nakagawa (NDC/JAERI).                         
00-04 Compilation for JENDL-3.3 was made by T.Nakagawa            
      Evaluated data of Maslov et al. /Ma97/ were extensively     
      adopted.                                                    
                                                                  
     ***** Modified parts from JENDL-3.2 *******************      
     All data                                                     
     *******************************************************      
                                                                  
================================================================= 
Modified parts from Maslov's evaluation.                          
================================================================= 
                                                                  
MF=2 Resonance Rapameters                                         
  MT=151                                                          
    Resolved resonance parameters (MLBW, 1.0E-5 - 500 eV)         
       Taken from JENDL-3.2.                                      
      **** Comment to JENDL-3.2 *****                             
      ENERGY RANGE IS FROM 1.0E-5 EV TO 500 EV. PARAMETERS WERE   
      TAKEN FROM THE FOLLOWING EXPERIMENTAL DATA.                 
         49 RESONANCES ABOVE 10 EV : SILBERT /Si73/               
          4 RESONANCES BELOW 10 EV : YOUNG /Yo67/                 
      THE PARAMETERS OF TWO NEGATIVE AND 2.9-EV RESONANCES WERE   
      ADJUSTED TO THE THERMAL CROSS SECTIONS/Mu84/                
                                                                  
    Unresolved resonance parameters (500 eV - 44.2668 keV)        
       The level spacing was modified to keep consistency with    
       that of L=0 and J=0.5. The neutron width was also modified 
       with the same factor of the level spacing. Interpolation   
       of cross sections was changed to 5 (log-log).              
       Background cross section was given to MT=18 to connect the 
       fission cross section above the unresolved resonance       
       region and cross sections calculated from the unresolved   
       resonance parameters.                                      
                                                                  
    Calculated Thermal cross sections and Resonance integral      
                                                                  
                 at .0253 eV (b)   Res. Integ. (b)                
       Total         586.7            -                           
       Elastic        28.6            -                           
       Fission        17.9            32.4                        
       Capture       540.3           152                          
                                                                  
MF=3 Neutron Cross Sections                                       
  MT=2   Elastic scattering                                       
    Calculated as Total - Sum of partial cross sections.          
                                                                  
  MT=18  Fission                                                  
    The fission cross section was adopted from JENDL-3.2.         
                                                                  
      ***** comment to JENDL-3.2 (MT=18) *****                    
      EVALUATED MAINLY ON THE BASIS OF DATA MEASURED BY           
      BUDTZ-JORGENSEN/Bu83/ OTHER EXPERIMENTS /Si73, Ba67, Fo67,  
      Er68, Dr70, Er70, Fo70, Sh72, Al88/ WERE ALSO TAKEN INTO    
      CONSIDERATION.                                              
      ****************************************                    
                                                                  
    NOTE: The data of MT's=19, 20 and 21 calculated by Maslov et  
    al. /Ma97/ were not adopted.                                  
                                                                  
  MT=102 Capture                                                  
    Direct and semi-direct capture cross section was calculated   
    with DSD code /Ka99/, and added to Maslov's calculation.      
                                                                  
MF=5 Energy Distributions of Secondary Neutrons                   
  MT=16, 17, 91                                                   
    At the threshold energies, the same shape of distributions at 
    the second incident energy was assumed.  Interpolation was    
    replaced with 22.                                             
                                                                  
  MT=455  Delayed Neutron Spectra                                 
    Results of summation calculation made by Brady and England    
    /Br89/ were adopted.                                          
                                                                  
================================================================= 
 Other parts are the same as Maslov's evaluation.                 
================================================================= 
                                                                  
REFERENCES                                                        
                                                                  
Al88) Alam B. et al.: Nucl. Sci. Eng., 99, 267 (1988).            
Ba67) Barton D.M. and Koonty P.G.: Phys. Rev., 162, 1070 (1967).  
Br89) Brady M.C. and England T.R.: Nucl. Sci. Eng., 103, 129      
    (1989).                                                       
Bu83) Budtz-Jorgensen C. et al.: 1982 Antwerp, 206 (1983).        
Dr70) Drake D.M. et al.: LA-4420, p.101 (1970).                   
Er68) Ermagambetov S.B. and Shirenkin G.N.: Sov. J. Nucl. Phys.,  
    25, 1364 (1968).                                              
Er70) Ermagambetov S.B. et al.: Sov. J. Nucl. Energy,29, 1190     
    (1970).                                                       
Fo67) Fomushkin E.F. et al.: Sov. J. Nucl. Phys., 5, 689 (1967).  
Fo70) Fomushkin E.F. et al.: Sov. J. Nucl. Phys., 10, 529 (1970). 
Ka99) Kawano T.: private communication (1999).                    
Ma97) Maslov V.M. et al.: INDC(BLR)-009/G (1997).                 
Mu84) Mughabghab S.F.: "Neutron Cross Sections, Vol. 1, Part B",  
    Academic Press (1984).                                        
Sh72) Shpak D.L. et al.: JETP Letters, 15, 228 (1972).            
Si73) Silbert M.G. et al.: Nucl. Sci. Eng., 52, 176 (1973).       
Yo67) Young T.E. et al.: Nucl. Sci. Eng., 30, 355 (1967).         
                                                                  
========== Description given in Maslov's data =================== 
                                                                  
 94-Pu-238 MINSK BYEL   EVAL-MAY97                                
                        DIST-JULY97                               
                                                                  
                      V.M. MASLOV, E.Sh. SUKHOVITSKIJ,            
                      Yu.V. PORODZINSKIJ, G.B. MOROGOVSKIJ        
                                                                  
 STATUS                                                           
 EVALUATION WAS MADE UNDER THE PROJECT AGREEMENT CIS-03-95        
 WITH INTERNATIONAL SCIENCE AND TECHNOLOGY CENTER (MOSCOW).       
 FINANCING PARTY OF THE ISTC FOR THE PROJECT IS JAPAN.            
 EVALUATION WAS REQUESTED BY JNDC (JAERI, TOKAI)                  
 DOCUMENTED IN INDC(BLR)-009, 1997.                               
                                                                  
 MF=1   GENERAL  INFORMATION                                      
                                                                  
   MT=451  COMMENTS AND DICTIONARY                                
   MT=452  TOTAL NUMBER OF NEUTRONS PER FISSION                   
           SUM OF MT=455 AND MT=456.                              
   MT=455  DELAYED NEUTRON DATA                                   
           NUMBER OF DELAYED NEUTRONS AND                         
           DECAY CONSTANTS FROM TUTTLE /1/ AND BRADY ET AL./2/    
   MT=456  NUMBER OF PROMPT NEUTRONS PER FISSION                  
           ABOVE  EMISSIVE FISSION THRESHOLD IS A                 
           SUPERPOSITION OF NEUTRON EMISSION                      
           IN (N,XNF) REACTIONS AND PROMPT FISSION                
           NEUTRONS.                                              
                                                                  
 MF=2   RESONANCE PARAMETERS                                      
                                                                  
   MT=151  RESONANCE  PARAMETERS  (MLBW)                          
           RESOLVED RESONANCE REGION :     1.0E-5 - 500 EV        
           PARAMETERS FOR BREIT-WIGNER FORMULA ARE BASED UPON     
           THE TOTAL CROSS SECTION MEASUREMENT BY YOUNG /3/;      
           THE FISSION CROSS SECTION MEASUREMENTS OF SILBERT      
           /4/, STUBBINS /5/, BUDTZ-JOERGENSEN /6/, ALAM /7/,     
           GERASIMOV /8/, DRAKE /9/;  CAPTURE CROSS               
           SECTION MEASUREMENT SILBERT /10/.                      
           CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE       
           INTEGRALS ARE:                                         
                            2200 M/SEC       RES.INTEG.           
              TOTAL         579.544 b            -                
              ELASTIC       21.965  b            -                
              FISSION       16.601  b         28.4497             
              CAPTURE       540.978 b         141.765             
                                                                  
           UNRESOLVED RESONANCE REGION :                          
           ENERGY INDEPENDENT PARAMETERS:                         
              R=9.238   FM   FROM OPTICAL MODEL CALCULATIONS      
              S1=2.399*10-4  FROM OPTICAL MODEL CALCULATIONS      
              S2=1.242*10-4  FROM OPTICAL MODEL CALCULATIONS      
           ENERGY   DEPENDENT PARAMETERS:                         
           S0-DECREASES FROM 1.036-4(0.50KEV) TO 0.968-4(44.27KEV)
           FISSION WIDTH FLUCTUATES TO FIT FISSION CROSS SECTION. 
           D - SPIN DEPENDENT, NORMALIZED TO  =8.301 EV     
           WITH ACCOUNT OF LEVEL MISSING /11/.                    
           WF -SPIN DEPENDENT AS DEFINED BY THE TRANSITION STATE  
           SPECTRA AT INNER AND OUTER BARRIER HUMPS, NORMALIZED   
           TO = 34 mEV TO FIT UNRESOLVED RESONANCE REGION  
           EXPERIMENTAL FISSION DATA.                             
           WG - FROM CASCADE MODEL WITH ACCOUNT OF FISSION AND    
           NEUTRON EMISSION COMPETITION, SPIN DEPENDENT. NORMA-   
           LIZED TO = 0.03485 EV.                          
                                                                  
 MF=3   NEUTRON CROSS SECTIONS                                    
                                                                  
   MT=1,4,51-69,91,102.  TOTAL, ELASTIC AND INELASTIC             
           SCATTERING, CAPTURE CROSS SECTION                      
           TOTAL,DIRECT ELASTIC AND DIRECT INELASTIC FOR MT=51,   
           52,53 AND OPTICAL TRANSMISSION COEFFICIENTS FROM       
           COUPLED CHANNELS CALCULATIONS.                         
           THE DEFORMED OPTICAL POTENTIAL USED:                   
           VR=(46.26-0.3*E) MEV    RR=1.26 FM  AR=0.615 FM        
           WD=(3.63+0.4*E)  MEV  E <  10 MEV    RD=1.24 FM        
           WD= 7.63 MEV          E=>  10 MEV    AD=0.5 FM         
           VSO=6.2 MEV RSO=1.12 FM ASO=0.47 FM  B2=0.197 B4=0.061 
           FOUR LEVELS OF ROTATIONAL GROUND STATE BAND            
           ARE COUPLED.                                           
           CAPTURE,COMPOUND ELASTIC AND INELASTIC BY STATISTICAL  
           MODEL, SEE MT=18-21                                    
           ABOVE NEUTRON ENERGY 5 MEV CAPTURE IS ASSUMED TO BE    
           CONSTANT.                                              
           ADOPTED LEVEL SCHEME OF PU-238 FROM NUCLEAR DATA       
           SHEETS /12/.                                           
                                                                  
             No       ENERGY(MEV)     SPIN-PARITY   K             
                                                                  
            g.s.       0.0               0   +      ?             
             1         0.04408           2   +      ?             
             2         0.14598           4   +      ?             
             3         0.30340           6   +      ?             
             4         0.51347           8   +      ?             
             5         0.60518           1   -      5             
             6         0.66143           3   -      6             
             7         0.76320           5   -      0             
             8         0.77280          10   +      0             
             9         0.94150           0   +      5             
            10         0.96277           1   -                    
            11         0.96810           2   -      6             
            12         0.98310           2   +      1             
            13         0.98546           2   -      1             
            14         1.02855           2   +      1             
            15         1.06995           3   +      3             
            16         1.07850          12   +      0             
            17         1.08257           4   -      0             
            18         1.12580           4   +                    
            19         1.13400           0   +      1             
                                                                  
                                                                  
          OVERLAPPING LEVELS ARE ASSUMED ABOVE 1.14 MEV           
          LEVEL DENSITY PARAMETERS: SEE MT 18-21                  
   MT=16,17.  (N,2N) AND (N,3N) CROSS SECTION                     
          FROM STATISTICAL MODEL CALCULATIONS /13/  WITH THE      
          ACCOUNT OF PRE-EQUILIBRIUM NEUTRON EMISSION:SEE MT=18-21
   MT=18,19,20,21.  FISSION CROSS SECTION IS CALCULATED WITHIN    
          STATISTICAL MODEL /14,15,16/ THE MEASURED DATA BY:      
          BUDTZ-JORGENSEN /6/, ALAM ET AL. /7/,                   
          ERMAGAMBETOV ET AL./17,18/, FOMUSHKIN ET AL./19,20/,    
          ARE FITTED.                                             
          THE FIRST CHANCE FISSION MT=19 IS CALCULATED WITH       
          THE CONTRIBUTION OF EMISSIVE FISSION TO TOTAL FISSION   
          CROSS SECTION ACCORDING TO /14/.                        
                                                                  
 MF=4   ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS               
                                                                  
        FOR MT=2, 55, 59  FROM COUPLED CHANNELS CALCULATIONS      
        WITH ADDED ISOTROPIC STATISTICAL CONTRIBUTION.            
                                                                  
        MT=16,17,18-21,54-69,91 - ISOTROPIC                       
                                                                  
 MF=5   ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                
                                                                  
        ENERGY DISTRIBUTIONS FOR MT=16,17 WERE                    
        CALCULATED BY STATISTICAL MODEL OF CASCADE NEUTRON        
        EMISSION TAKING INTO ACCOUNT THE HISTORY OF THE DECAY     
        WITH THE ALLOWANCE OF PRE-EQUILLIBRIUM EMISSION OF        
        THE FIRST NEUTRON /21/                                    
        ENERGY DISTRIBUTIONS FOR MT=18,19,20,21 WERE CALCULATED   
        WITH ACCOUNT OF COMPETITION                               
        BETWEEN MULTIPLE-CHANCE FISSION PROCESSES UP THROUGH      
        THIRD-CHANCE FISSION WITH THE ALLOWANCE OF PRE-EQUILIBRIUM
        EMISSION OF THE FIRST NEUTRON /21 /.                      
                                                                  
REFERENCES                                                        
 1. Tuttle R.J. Proc. Consultants Meeting on Delayed Neutron      
    Properties, 1979, Vienna, INDC(NDS)-107/G, p.29.              
 2. Brady M..C., Wright R.Q., England T.R., Report ORNL/CSD/TM-   
    226 (1991),  IAEA-NDS-1)2, 1992.                              
 3. Young T.E., Simpson F.B.,Berreth J.R., Coops M.S. Nucl. Sci.  
    Engng. 30, 355 (1967).                                        
 4. Silbert M.G., Moat A., Young T.E. Nucl.Sci.Eng. 52, 176 (1973)
 5. Stubbins W.F., Bowman C.D., Auchampaugh G.F., Coops M.F.      
    Phys. Rev. 154, 1111 (1967).                                  
 6. Budtz-Jorgensen C., Knitter H.H. and Smith D.L. Proc.Int.     
    Conf. Nuclear Data for Science and Technology, Antwerpen,     
    Belgium, September 6-10, 1982, p. 206,  ?  del Publishing Co. 
    Boston (1983).                                                
 7. Alam B., Block R.C., Slovacek R.E., Hoff R.W. Nucl. Sci. Eng. 
    99, 267 (1988).                                               
 8. Gerasimov V.F., Sov.J.Nucl.Phys., 4, 706 (1967).              
 9. Drake D.M. et al. LA-4420, p.101, 1970.                       
10. Silbert M.G., Berreth J.R. Nucl. Sci. Eng., 52, 187 (1973).   
11. Porodzinskij Yu.V., Sukhovitskij E.Sh. and Maslov B.M. Int.   
    Conf. Nuclear Data for Science and Technology, Trieste,       
    Italy, May 19-24, 1997, to be published.                      
12. ENSDF, 1995.                                                  
13. Ignatjuk A.V., Maslov V.M., Pashchenko A.B. Sov.J.Nucl.Phys.  
    47, 224 (1988).                                               
14. Ignatjuk A.V., Maslov V.M., Proc.Int.Symp.Nuclear Data        
    Evaluation Methodology, Brookhaven, USA, October 12-16,       
    p.440, World Scientific, 1993.                                
15. Maslov B.M., Kikuchi Y. JAERI-Research 96-030, June, 1996.    
16. Maslov B.M. Int.Conf.Nuclear Data for Science And Technology, 
    Trieste, Italy, May 19-24, 1997, to be published.             
17. Ermagambetov S.V., Smirenkin G.N. Sov.At.Energy, 25, 1364     
    (1968).                                                       
18. Ermagambetov S.V., Smirenkin G.N. JETP Letters, 9, 309 (1969).
19. Fomushkin E.F., Gutnikova E.K. Sov.J.Nucl.Phys., 10, 529      
    (1970).                                                       
20. Fomushkin E.F., Gutnikova E.K., Zamyatnin Yu.S. et al.        
    Sov.J.Nucl.Phys., 5, 966 (1967).                              
21. Maslov B.M, Porodzinskij Yu.V., Sukhovitskij E.Sh., Proc.     
    Int.Conf. on Neutron Physics, 14-18 Sept., Kiev, USSR, v.1,   
    p.413, 1988.