24-Cr- 50

 24-CR- 50 NEDAC      EVAL-MAR87 T.ASAMI(NEDAC)                   
                      DIST-SEP89 REV2-SEP93                       
----JENDL-3.2         MATERIAL 2425                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
87-03  NEW EVALUATION WAS MADE BY T.ASAMI.                        
88-12  MF/MT=3/107 MODIFIED.                                      
93-09  JENDL-3.2.                                                 
       COMPILED BY T.NAKAGAWA (NDC/JAERI)                         
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (4,16-28), (4,91)    TAKEN FROM JENDL FUSION FILE           
      (5,16-91)            TAKEN FROM JENDL FUSION FILE           
     ***********************************************************  
                                                                  
     -------------------------------------------------------------
      JENDL FUSION FILE /1/  (AS OF SEP. 1993)                    
        EVALUATED B.YU (CIAE) AND S.CHIBA (NDC/JAERI)             
        COMPILED BY B.YU.                                         
                                                                  
          ALL OF CROSS SECTIONS WERE TAKEN FROM JENDL-3.  MF=6 OF 
        MT=16, 22, 28 AND 91 WERE CREATED WITH SINCROS-II /2/ AND 
        F15TOB/1/ PROGRAM.  MODIFIED-KUMABE'S SYSTEMATICS /1/ WAS 
        USED.  THE PRECOMPOUND/COMPOUND RATIO WAS CALCULATED BY   
        THE SINCROS-II CODE SYSTEM.                               
          OPTICAL-MODEL, LEVEL DENSITY AND OTHER PARAMETERS USED  
        IN THE SINCROS-II CALCULATION ARE DESCRIBED IN REF./2/.   
        LEVEL SCHEMES WERE DETERMINED ON THE BASIS OF ENSDF/3/.   
     -------------------------------------------------------------
                                                                  
                                                                  
MF=1  GENERAL INFORMATION                                         
 MT=451  DESCRIPTIVE DATA AND DICTIONARY                          
                                                                  
MF=2  RESONANCE PARAMETERS                                        
 MT=151  RESOLVED RESONANCE PARAMETERS                            
   RESOLVED PARAMETERS FOR MLBW FORMULA WERE GIVEN IN THE ENERGY  
   REGION FROM 1.0E-5 EV TO 300 KEV.  EVALUATION WAS BASED ON THE 
   EXPERIMENTAL DATA OF STIEGLITZ+71/4/, BEER+74/5/, ALLEN+77/6/, 
   KENNY+77/7/ AND BRUSEGAN+86/8/.  EFFECTIVE SCATTERING RADIUS = 
   5.0 FM/9/.                                                     
                                                                  
    CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRAL.    
            2200 M/S CROSS SECTION(B)     RES. INTEGRAL(B)        
    ELASTIC      2.31                                             
    CAPTURE     15.9                          7.41                
    TOTAL       18.2                                              
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
    BELOW 300 KEV, ZERO BACKGROUND CROSS SECTION WAS GIVEN.       
                                                                  
 MT=1 TOTAL                                                       
    OPTICAL AND STATISTICAL MODEL CALCULATION WAS MADE WITH THE   
    CASTHY CODE/10/. THE OPTICAL POTENTIAL PARAMETERS USED ARE:   
      V = 46.78 - 0.262*EN,    VSO = 7.0    (MEV)                 
     WS = 4.87 + 0.352*EN,      WV = 0      (MEV)                 
      R = 1.30,  RS = 1.40,  RSO = 1.30     (FM)                  
      A = 0.55,  B = 0.40,   ASO = 0.48     (FM)                  
       SURFACE IMAGINARY PART IS IN DERIVATIVE WOODS-SAXON FORM.  
                                                                  
 MT=2 ELASTIC SCATTERING                                          
    OBTAINED BY SUBTRACTING THE SUM OF THE PARTIAL CROSS SECTIONS 
    FROM THE TOTAL CROSS SECTION.                                 
                                                                  
 MT=4, 51-55, 91 INELASTIC SCATTERING                             
    CALCULATED WITH THE CASTHY CODE/10/, TAKING ACCOUNT OF THE    
    CONTRIBUTION FROM THE COMPETING PROCESSES AND USING THE       
    DISCRETE LEVEL DATA/11/ SHOWN BELOW.  THE CONTRIBUTIONS FROM  
    THE DIRECT PROCESS FOR THE LEVEL MARKED WITH '*' WERE CALCULA-
    TED WITH THE DWUCK CODE/12/. THE DEFORMATION PARAMETERS USED  
    IN THE CALCULATION WERE ASSUMED BASED ON PETERSON'S DATA/13/. 
                                                                  
              LEVEL ENERGY(MEV)   SPIN-PARITY                     
        G.S.      0.0                 0+                          
          1       0.7833              2+          *               
          2       1.8814              4+          *               
          3       2.9245              2+          *               
          4       3.1611              2+          *               
          5       3.1641              6+                          
          6       3.3247              4+                          
          7       3.5946              4+                          
          8       3.6101              4+                          
          9       3.6295              1+                          
         10       3.6940              0+                          
         11       3.6978              2+                          
         12       3.7924              5+                          
         13       3.8261              6+                          
         14       3.8443              3+                          
         15       3.8500              0+                          
         16       3.8752              6+                          
         17       3.8953              2+                          
         18       3.8983              4+                          
         19       3.9377              3+                          
         20       4.0517              0+                          
       LEVELS ABOVE 4.066 MEV WERE ASSUMED TO BE OVERLAPPING.     
                                                                  
    THE CALCULATED DATA FOR THE INELASTIC SCATTERING WERE FINALLY 
    LUMPED FOR THE CONVENIENCE ON THE CONSTRUCTION OF THE ELEMENTA
    DATA AS FOLLOWS:                                              
                                                                  
       MT NO.    LEVEL ENERGY(MEV)  LUMPING OF LEVEL              
         51         0.7833                1                       
         52         1.8814                2                       
         53         2.9245                3                       
         54         3.1611               4-5                      
         55         3.3247                6                       
         91         3.5946             OVER 7                     
                                                                  
    FURTHERMORE, THE DATA OF MT=51 WERE MODIFIED BY CONSIDERING   
    EXPERIMENTAL DATA.  THE TOTAL INELASTIC SCATTERING CROSS SEC- 
    TION (MT=4) IS THE SUM OF MT'S FROM 51 TO 91.                 
                                                                  
 MT=16       (N,2N)                                               
    MAINLY BASED ON THE EXPERIMENTAL DATA OF BORMANN /14/.        
 MT=22       (N,NA)                                               
    CALCULATED WITH THE GNASH CODE/15/.                           
 MT=28       (N,NP)                                               
    CALCULATED WITH THE GNASH CODE/15/.                           
 MT=102      CAPTURE                                              
    CALCULATED WITH THE CASTHY CODE/10/ AND NORMALIZED TO         
    REPRODUCE THE ELEMENT DATA OF 10 MB AT 50 KEV.                
 MT=103      (N,P)                                                
    CALCULATED WITH THE GNASH CODE/15/.                           
 MT=107      (N,A)                                                
    CALCULATED WITH THE GNASH CODE AND NORMALIZED AT 14.8 MEV IN  
    REFERRING TO GRIMES'S DATA/16/. THE DATA NEAR THE THRESHOLD   
    WERE MODIFIED IN REFERRING TO THE EXPERIMENTAL DATA FOR THE   
    ELEMENT CR(N,ALPHA)/17/.                                      
 MT=251      MU-BAR                                               
    CALCULATED WITH OPTICAL MODEL.                                
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
 MT=2   ELASTIC SCATTERING                                        
    CALCULATED WITH THE CASTHY CODE/10/.                          
 MT=16, 22, 28, 91   (N,2N), (N,NA), (N,NP), CONTINUUM INELASTIC  
    APPROXIMATELY TRANSFORMED FROM THE MF=6 DATA (DDX) OF JENDL   
    FUSION FILE.                                                  
 MT=51-55   INELASTIC SCATTERING                                  
    CALCULATED WITH THE CASTHY CODE AND THE DWUCK CODE/12/.       
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
 MT=16, 22, 28, 91                                                
    APPROXIMATELY TRANSFRMED FROM THE MF=6 DATA (DDX) OF JENDL    
    FUSION FILE.                                                  
                                                                  
REFERENCES                                                        
 1) CHIBA S. ET AL.: JAERI-M 92-027, P.35 (1992).                 
 2) YAMAMURO N.: JAERI-M 90-006 (1990).                           
 3) ENSDF: EVALUATED NUCLEAR STRUCTURE DATA FILE, BNL/NNDC.       
 4) STIEGLIZ R.G. ET AL. : NUCL. PHYS. A163, 592 (1971).          
 5) BEER H. AND SPENCER R.P. : KFK-2063 (1974), ALSO NUCL.        
    PHYS. A240, 29 (1975).                                        
 6) ALLEN B.J. AND MUSGROVE A.R.DE L. : NEUTRON DATA OF           
    STRUCTURAL MATERIALS FOR FBR, 1977 GEEL MEETING, P.447,       
    PERGAMON PRESS (1979).                                        
 7) KENNY M.J. ET AL. : AAEC/E-400 (1977).                        
 8) BRUSEGAN A. ET AL. : 85SANTA FE VOL.1 P.633 (1986).           
 9) MUGHABGHAB S.F. ET AL. : "NEUTRON CROSS SECTIONS", VOL.1,     
    PART A (1981).                                                
10) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                
11) DATA TAKEN FROM ENSDF(EVALUATED NUCLEAR STRUCTURE DATA FILE). 
12) KUNZ P.D. : UNPUBLISHED.                                      
13) PETERSON R.J. AND PERLMAN, D.E.: NUCL. PHYS. A117,185(1968).  
14) BORMANN M. : THE DATA (1965) IN EXFOR FILE.                   
15) YOUNG P.G. AND ARTHUR E.D. : LA-6947 (1977).                  
16) GRIMES S.M. ET AL. : PHYS. REV. C19, 2127 (1979).             
17) PAULSEN A. : NUCL. SCI. ENG. 78, 377 (1981).