24-Cr- 53

 24-CR- 53 NEDAC      EVAL-MAR87 T.ASAMI(NEDAC)                   
                      DIST-SEP89 REV2-SEP93                       
----JENDL-3.2         MATERIAL 2434                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
87-03  NEW EVALUATION WAS MADE FOR JENDL-3                        
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 120 KEV.  EVALUATED BASED ON THE      
   EXPERIMENTAL DATA OF STIEGLITZ+71/4/, BEER+74/5/, ALLEN+77/6/, 
   KENNY+77/7/, BRUSEGAN+86/8/ AND MUELLER+71/9/.  EFFECTIVE      
   SCATTERING RADIUS = 5.4 FM/10/.                                
                                                                  
    CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRAL.    
            2200 M/S CROSS SECTION(B)     RES. INTEGRAL(B)        
    ELASTIC      7.78                                             
    CAPTURE     18.2                           8.61               
    TOTAL       25.9                                              
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
   BELOW 120 KEV, NO BACKGROUND CROSS SECTION WAS GIVEN.          
   ABOVE 120 KEV, THE TOTAL AND PARTIAL CROSS SECTIONS WERE GIVEN 
   POINTWISE.                                                     
                                                                  
 MT=1 TOTAL                                                       
    OPTICAL AND STATISTICAL MODEL CALCULATION WAS MADE WITH       
    THE CASTHY CODE/11/. 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, 51-63, 91 INELASTIC SCATTERING                             
    CALCULATED WITH THE CASTHY CODE/11/, TAKING ACCOUNT OF THE    
    CONTRIBUTION FROM THE COMPETING PROCESSES AND USING THE       
    DISCRETE LEVEL DATA/3/ SHOWN BELOW.  THE CONTRIBUTIONS FROM   
    THE DIRECT PROCESS FOR THE LEVELS MARKED WITH '*' WERE        
    CALCULATED WITH THE DWUCK CODE/12/. THE DEFORMATION PARAME-   
    TERS USED IN THE CALCULATION WERE ASSUMED BASED ON A WEAK     
    COUPLING MODEL.                                               
                                                                  
              LEVEL ENERGY(MEV)   SPIN-PARITY                     
        G.S.      0.0                3/2-                         
          1       0.5640             1/2-       *                 
          2       1.0063             5/2-       *                 
          3       1.2895             7/2-       *                 
          4       1.5366             7/2-       *                 
          5       1.9736             5/2-       *                 
          6       2.1724            11/2-                         
          7       2.2330             9/2-                         
          8       2.3208             3/2-                         
          9       2.4531             3/2-                         
         10       2.6570             5/2-                         
         11       2.6695             1/2-                         
         12       2.7065            13/2-                         
         13       2.7080             3/2-                         
         14       2.7720             5/2-                         
         15       2.8266            11/2-                         
         16       2.9930             7/2-                         
         17       3.0841            15/2-                         
         18       3.0930             5/2-                         
         19       3.1380             5/2-                         
         20       3.1793             3/2-                         
         21       3.2439            11/2-                         
         22       3.2610             5/2-                         
       LEVELS ABOVE 3.435 MEV WERE ASSUMED TO BE OVERLAPPING.     
                                                                  
  THE CALCULATED DATA FOR THE INELASTIC SCATTERING WERE FINALLY   
  LUMPED FOR THE CONVENIEINCE ON THE CONSTRUCTION OF THE ELEMENT  
  DATA AS FOLLOWS:                                                
                                                                  
       MT NO.    LEVEL ENERGY(MEV)  LUMPING                       
         51         0.5640            1                           
         52         1.0063            2                           
         53         1.2895            3                           
         54         1.5366            4                           
         55         1.9736            5                           
         56         2.1724            6                           
         57         2.2330            7                           
         58         2.3208            8                           
         59         2.4531            9                           
         60         2.6570          10-13                         
         61         2.7720           14                           
         62         2.8266           15                           
         63         2.9930           16                           
         91         2.9930         OVER 17                        
                                                                  
 MT=16       (N,2N)                                               
    CALCULATED WITH THE GNASH CODE/13/.                           
 MT=22       (N,NA)                                               
    CALCULATED WITH THE GNASH CODE AND NORMALIZED.                
 MT=28       (N,NP)                                               
    CALCULATED WITH THE GNASH CODE AND NORMALIZED.                
 MT=102      CAPTURE                                              
    CALCULATED WITH THE CASTHY CODE/11/ AND NORMALIZED AT 50 KEV  
    TO REPRODUCE THE ELEMENT DATA OF 10 MB.                       
 MT=103      (N,P)                                                
    BELOW 9 MEV, EVALUATED BASED ON THE EXPERIMENTAL DATA OF      
    SMITH/14/.  ABOVE 9 MEV, CALCULATED WITH THE GNASH CODE/13/   
    AND NORMALIZED SO AS TO BE CONNECTED WITH SMITH'S EXPERIMENTAL
    DATA/14/.                                                     
 MT=107      (N,A)                                                
    CALCULATED WITH THE GNASH CODE/13/ AND NORMALIZED AT 14.7 MEV 
    TO DOLJA'S EXPERIMENTAL DATA/15/. THE DATA NEAR THRESHOLD     
    WERE MODIFIED IN REFERRING TO THE EXPERIMENTAL DATA FOR THE   
    ELEMENT CR(N,ALPHA)/16/.                                      
 MT=251      MU-BAR                                               
    CALCULATED WITH OPTICAL MODEL.                                
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
 MT=2   ELASTIC SCATTERING                                        
    CALCULATED WITH THE CASTHY CODE/11/.                          
 MT=51-63   INELASTIC SCATTERING                                  
    CALCULATED WITH THE CASTHY CODE AND THE DWUCK CODE/12/.       
 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.                                                  
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
 MT=16, 22, 28, 91                                                
    APPROXIMATELY TRANSFORMED 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) MUELLER K.N. ET AL.: NUCL. PHYS. A164, 97 (1971).             
10) MUGHABGHAB S.F. ET AL.: "NEUTRON CROSS SECTIONS", VOL.1,      
    PART A (1981).                                                
11) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                
12) KUNZ P.D.: UNPUBLISHED.                                       
13) YOUNG P.G. AND ARTHUR E.D.: LA-6947 (1977).                   
14) SMITH D.L. ET AL.: NUCL. SCI. ENG. 78, 420 (1981).            
15) DOLJA G.D. ET AL.: 1973 KIEV CONF. VOL.3, 131 (1973).         
16) PAULSEN A.: NUCL. SCI. ENG. 78, 377 (1981).