26-Fe- 0

 26-FE-  0 JNDC       EVAL-MAR87 S.IIJIMA,H.YAMAKOSHI             
                      DIST-SEP89 REV2-MAR94                       
----JENDL-3.2         MATERIAL 2600                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
87-03  EVALUATION WAS PERFORMED FOR JENDL-3.                      
87-05  COMPILED BY K.SHIBATA (JAERI).                             
*****  JENDL-3.2  ************************************************
92-09  MODIFICATION WAS MADE FOR TOTAL AND ELASTIC SCATTERING     
       CROSS SECTIONS.                                            
93-11  THE RESONACE PARAMETERS OF FE-58 WERE MODIFIED.            
       INEALSTIC SCATTERING CROSS SECTIONS WERE REEVALUATED BY    
       K. SHIBATA (JAERI).  DISCRETE LEVELS WERE LUMPED SO THAT   
       REACTION KINEMATICS COULD BE PROPERLY TAKEN INTO ACCOUNT.  
       FILES 4 AND 5 FOR MT=16,22,28,91 WERE OBTAINED FROM THE    
       FILE-6 OF THE JENDL FUSION FILE /16/.                      
       GAMMA PRODUCTION DATA WERE REVALUATED BY S.IGARASI (NEDAC).
94-03  FOR (3,3),(3,107),(13,107), SMALL CROSS-SECTION VALUES     
       WERE REPLACED WITH 0.0.                                    
******************************************************************
                                                                  
NATURAL IRON DATA CONSTRUCTED FROM FE-ISOTOPES.                   
                                                                  
MF=1  GENERAL INFORMATION                                         
  MT=451  DESCRIPTIVE DATA AND DICTIONARY                         
                                                                  
MF=2  RESONANCE PARAMETERS                                        
  MT=151 RESOLVED RESONANCES                                      
      RESONANCE REGION = 1.0E-5 EV TO 250.0 KEV                   
      THE MULTILEVEL BREIT-WIGNER FORMULA WAS USED.  PARAMETERS   
      WERE ADOPTED FROM THE FOLLOWING SOURCES.                    
         FE-54 : PANDEY+/1/ FOR 0 - 680 KEV. R=5.6 FM             
         FE-56 : PEREY+/2/ FOR -2.0 - 400 KEV. R=5.4 FM FROM FIT- 
                 TING TO TOTAL CROSS SECTION BELOW 60 KEV.        
                 PARAMETERS OF THE 1.15 KEV RESONANCE WERE        
                 TAKEN FROM THE RESULT OF THE NEANDC TASK         
                 FORCE /3/.                                       
         FE-57 : ALLEN+/4/ FOR S-WAVE RESONANCES, AND BEER+/5/    
                 FOR P-WAVE RESONANCES IN 0 - 185 KEV.            
         FE-58 : MUGHABGHAB+/6/.                                  
      FOR FE-56, A NEGATIVE LEVEL WAS ADDED AT -3.75 KEV WITH     
      NEUTRON WIDTH OF 100 EV AND GAMMA WIDTH OF 1.0 EV.  NEUTRON 
      WIDTH OF 27.67-KEV RESONANCE WAS TAKEN AS 1420 EV.          
                                                                  
      CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS.      
                      2200-M/S     RES. INTEG.                    
         ELASTIC      11.36  B         -                          
         CAPTURE       2.56  B        1.340 B                     
         TOTAL        13.92  B         -                          
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
      BELOW 250 KEV, BACKGROUND CROSS SECTIONS WERE GIVEN.        
                                                                  
  MT=1    TOTAL                                                   
      FOR ENERGIES 250 KEV - 20 MEV, FINE RESOLUTION DATA WERE    
      TAKEN BY EYE-GUIDE USING INTERACTIVE DISPLAY OF NDES (      
      NEUTRON DATA EVALUATION SYSTEM) DEVELOPED BY T.NAKAGAWA AT  
      THE NUCLEAR DATA CENTER, JAERI.  THE FOLLOWING DATA WERE    
      MAINLY ADOPTED:                                             
           BELOW 500 KEV    : PATTENDEN+/12/                      
           500 KEV - 4.7MEV : CARLSON+/7/                         
           4.7 MEV - 12 MEV : CIERJACKS+/8/                       
      BY CONSIDERING EXPERIMENTAL RESOLUTION, CROSS SECTION SHAPE 
      WAS MADE SHARPER.                                           
  MT=2    ELASTIC SCATTERING                                      
      GIVEN AS TOTAL MINUS NONELASTIC CROSS SECTIONS              
  MT=3    NONELASTIC                                              
      SUM OF MT=4,16,22,28,102,103,107                            
  MT=16,22,28,103                                                 
      CALCULATED USING GNASH /9/.                                 
  MT=4,51-90,91  INELASTIC SCATTERING                             
      ISOTOPIC DATA WERE OBTAINED FROM THE CASTHY/10/ AND GNASH   
      CALCULATIONS.  ISOTOPIC LEVELS WERE GROUPED INTO 25         
      LEVELS OF NATURAL ELEMENT.  THE CONTRIBUTIONS FROM THE      
      DIRECT PROCESS WERE INCLUDED IN THE LEVELS OF MT=55,58,     
      64,66,68,69,88,90.                                          
      OPTICAL POTENTIAL PARAMETERS USED IN THE CALCULATION ARE    
      AS FOLLOWS:                                                 
           V  = 46.0-0.25*E              , R0=1.286, A0=0.620     
           WS = 14.0-0.2*E               , RS=1.390, AS=0.700     
                14.8-0.2*E FOR FE-57                              
           VSO= 6.0                      , RSO=1.07 ,ASO=0.620    
             ENERGIES IN MEV UNIT, LENGTHS IN FM UNIT.            
      *****  JENDL-3.2  **************************************    
      FOR MT=51, RESONANCE STRUCTURE OF FE-57 WAS TAKEN INTO      
      ACCOUNT.                                                    
      MT=55 (1ST LEVEL OF FE-56)                                  
        850 KEV - 2.15 MEV                                        
          EVALUATED ON THE BASIS OF THE MEASUREMENTS/12,13/.      
        2.15 MEV - 4.6 MEV                                        
          MODIFIED BY CONSIDERING THE JENDL-2 DATA.               
      MT=61,66,68,70 (2ND,3RD,4TH AND 5TH LEVELS OF FE-56)        
        THESE CROSS SECTIONS WERE MODIFIED AROUNF THRESHOLD BY    
        CONSIDERING THE MEASUREMENTS/14,15/.                      
      MT=68,70,76-79,81-85,88,91                                  
        ABOVE 10 MEV, THESE CROSS SECTIONS WERE SLIGHTLY MODIFIED 
        ACCORDING TO THE JENDL FUSION FILE/16/, WHICH WAS         
        OBTAINED FROM SINCROS-II /17/ CALCULATIONS.               
      ********************************************************    
                                                                  
  MT=102  CAPTURE                                                 
       BACKGROUND CROSS SECTION WAS GIVEN BELOW 250 KEV.          
       ABOVE 250 KEV, THE CASTHY CALCULATION WAS ADOPTED.         
  MT=107      (N,ALPHA)                                           
      FOR FE-56, THE EVALUATION WAS MADE ON THE BASIS OF          
      EXPERIMENTAL DATA.  FOR FE-54,57,58, THE GNASH CALCULATION  
      WAS ADOPTED.                                                
  MT=251  MU-BAR                                                  
      CALCULATED WITH CASTHY /10/.                                
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2,51-90                                                      
      OPTICAL AND STATISTICAL-MODEL CALCULATIONS.                 
      THE C.C. CALCULATIONS WERE ADDED TO THE LEVELS OF MT=55,    
      58,61,63,64,65,70,73,74.                                    
  MT=16,22,28,91                                                  
      OBTAINED FROM JENDL FUSION FILE.                            
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
  MT=16,22,28,91                                                  
      OBTAINED FROM JENDL FUSION FILE.                            
                                                                  
MF=12 PHOTON MULTIPLICITIES                                       
  MT=3                                                            
      MULTIPLICITIES WERE CALCULATED USING GNASH.                 
  MT=102                                                          
      CALCULATED WITH CASTHY.                                     
                                                                  
MF=13 PHOTON PRODUCTION CROSS SECTIONS                            
  MT=4,103,107                                                    
      BELOW 2.5 MEV, DISCRETE GAMMAS WERE GIVEN.                  
                                                                  
MF=14 PHOTON ANGULAR DISTRIBUTIONS                                
  MT=3,4,102,103,107                                              
      ASSUMED TO BE ISOTROPIC.                                    
                                                                  
MF=15 PHOTON ENERGY DISTRIBUTIONS                                 
  MT=102                                                          
      BELOW 10 KEV, CALCULATED WITH CASTHY.                       
      ABOVE 10 KEV, BASED ON THE DATA OF IGASHIRA ET AL./11/.     
  MT=3,103,107                                                    
      CALCULATED WITH GNASH.                                      
                                                                  
REFERENCES                                                        
 1) PANDEY M.S. ET AL.: PROC. CONF. NUCLEAR CROSS SECTIONS AND    
    TECHNOLOGY, WASHINGTON D.C., (1975), P.748.                   
 2) PEREY F.G. ET AL.: PROC. SPECIALIST MEETING ON NEUTRON DATA   
    OF STRUCTURAL MATERIALS FOR FAST REACTORS, GEEL, (1977),      
    P.530.                                                        
 3) NAKAJIMA Y.: JAERI-M 85-035, P.196 (1985).                    
 4) ALLEN B.J. ET AL.: PROC. SPECIALIST MEETING ON NEUTRON DATA   
    OF STRUCTURAL MATERIALS FOR FAST REACTORS, GEEL, (1977),      
    P.476.                                                        
 5) BEER H. AND SPENCER R.R.: KFK-2063 (1974).                    
 6) MUGHABGHAB S.F. ET AL.: "NEUTRON CROSS SECTIONS, VOL. 1,      
    PART A", ACADEMIC PRESS (1981).                               
 7) CARLSON A.D. AND CERBONE R.J.: NUCL. SCI. ENG., 42, 28        
    (1970).                                                       
 8) CIERJACKS S. ET AL.: KFK-1000 (1968).                         
 9) YOUNG P.G. AND ARTHUR E.D.: LA-6947 (1977).                   
10) IGARASI S. : J. NUCL. SCI. TECHNOL., 12, 67 (1975).           
11) IGASHIRA M. ET AL.: PROC. INT. CONF. NUCLEAR DATA FOR         
    SCIENCE AND TECHNOLOGY, MITO, 1988, P.67, (1988).             
12) VOSS F. ET AL.: PROC. INT. CONF. ON NEUTRON CROSS SECTIONS    
    AND TECHNOLOGY, KNOXVILLE 1971, P.191 (1971).                 
13) SMITH D.L.: ANL/NDM-20 (1976).                                
14) HOPKINS J.C. AND SILBERT M.G.: NUCL. SCI. ENG.,19,431(1964).  
15) GILBOY W.B. AND TOWLE J.H.: NUCL. PHYS., 64, 130 (1965).      
16) CHIBA S. ET AL.: JAERI-M 92-027, P.35 (1992).                 
17) YAMAMURO N.: JAERI-M 90-006 (1990).