55-Cs-137

 55-CS-137 JNDC       EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.        
                      DIST-MAR02 REV3-FEB02            20020222   
----JENDL-3.3         MATERIAL 5537                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
   ===========================================================    
   JENDL-3.2 data were automatically transformed to JENDL-3.3.    
    Interpolation of spectra: 22 (unit base interpolation)        
    (3,251) deleted, T-matrix of (4,2) deleted, and others.       
   ===========================================================    
                                                                  
HISTORY                                                           
84-10 EVALUATION FOR JENDL-2 WAS MADE BY JNDC FPND W.G./1/        
90-03 MODIFICATION FOR JENDL-3 WAS MADE/2/.                       
93-03 JENDL-3.2 WAS MADE BY JNDC FPND W.G.                        
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (2,151)       ALL RESOLVED RESONANCES WERE DELETED.         
      (3,1), (3,2), (3102)                                        
                    BELOW 1.7 KEV                                 
     ***********************************************************  
                                                                  
                                                                  
MF = 1  GENERAL INFORMATION                                       
  MT=451 COMMENTS AND DICTIONARY                                  
                                                                  
MF = 2  RESONANCE PARAMETERS                                      
  MT=151 UNRESOLVED RESONANCE PARAMETERS                          
    RESOLVED RESONANCE PARAMETERS GIVEN IN JENDL-3.1 WERE DELETED.
    ONLY UNRESOLVED RESONANCE PARAMETERS WERE GIVEN.  THE LOWER   
    ENERGY BOUNDARY WAS DETERMINED SO AS TO REPRODUCE THE CAPTURE 
    RESONANCE INTEGRAL OF 0.35+-0.07 B MEASURED BY HARADA ET AL.  
    /3/                                                           
                                                                  
  UNRESOLVED RESONANCE REGION : 1.70 KEV - 100 KEV                
    THE NEUTRON STRENGTH FUNCTIONS, S0, S1 AND S2 WERE CALCULATED 
    WITH OPTICAL MODEL CODE CASTHY/4/.                            
    THE OBSERVED LEVEL SPACING WAS DETERMINED TO REPRODUCE THE    
    CAPTURE CROSS SECTION CALCULATED WITH CASTHY.  THE EFFECTIVE  
    SCATTERING RADIUS WAS OBTAINED FROM FITTING TO THE CALCULATED 
    TOTAL CROSS SECTION AT 100 KEV.  THE RADIATION WIDTH GG WAS   
    BASED ON THE SYSTEMATICS OF MEASURED VALUES FOR NEIGHBORING   
    NUCLIDES.                                                     
                                                                  
  TYPICAL VALUES OF THE PARAMETERS AT 70 KEV:                     
    S0 = 1.800E-4, S1 = 1.100E-4, S2 = 1.600E-4, SG = 0.801E-4,   
    GG = 0.090 EV, R  = 5.101 FM.                                 
                                                                  
  CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS)   
                     2200 M/S               RES. INTEG.           
      TOTAL           3.780                    -                  
      ELASTIC         3.530                    -                  
      CAPTURE         0.250                     0.357             
                                                                  
MF = 3  NEUTRON CROSS SECTIONS                                    
                                                                  
- BELOW 1.7 KEV:  THE ELASTIC SCATTRING CROSS SECTION IS          
  CALCULATED FROM R = 5.3 FM.  THE CAPTURE CROSS SECTION IS IN    
  THE FORM OF 1/V AND 0.250 B AT 0.0253 EV/3/.  THE TOTAL CROSS   
  SECTION IS SUM OF THESE TWO.                                    
                                                                  
- BETWEEN 1.7 KEV AND 100 KEV: URP GIVEN.                         
                                                                  
- ABOVE 100 KEV, THE SPHERICAL OPTICAL AND STATISTICAL MODEL      
  CALCULATION WAS PERFORMED WITH CASTHY, BY TAKING ACCOUNT OF     
  COMPETING REACTIONS, OF WHICH CROSS SECTIONS WERE CALCULATED    
  WITH PEGASUS/5/ STANDING ON A PREEQUILIBRIUM AND MULTI-STEP     
  EVAPORATION MODEL.  THE OMP'S FOR NEUTRON GIVEN IN TABLE 1 WERE 
  DETERMINED BY IGARASI ET AL./6/ TO REPRODUCE A SYSTEMATIC TREND 
  OF THE TOTAL CROSS SECTION.  THE OMP'S FOR CHARGED PARTICLES    
  ARE AS FOLLOWS:                                                 
     PROTON   = PEREY/7/                                          
     ALPHA    = HUIZENGA AND IGO/8/                               
     DEUTERON = LOHR AND HAEBERLI/9/                              
     HELIUM-3 AND TRITON = BECCHETTI AND GREENLEES/10/            
  PARAMETERS FOR THE COMPOSITE LEVEL DENSITY FORMULA OF GILBERT   
  AND CAMERON/11/ WERE EVALUATED BY IIJIMA ET AL./12/  MORE       
  EXTENSIVE DETERMINATION AND MODIFICATION WERE MADE IN THE       
  PRESENT WORK.  TABLE 2 SHOWS THE LEVEL DENSITY PARAMETERS USED  
  IN THE PRESENT CALCULATION.  ENERGY DEPENDENCE OF SPIN CUT-OFF  
  PARAMETER IN THE ENERGY RANGE BELOW E-JOINT IS DUE TO GRUPPELAAR
  /13/.                                                           
                                                                  
  MT = 1  TOTAL                                                   
    SPHERICAL OPTICAL MODEL CALCULATION WAS ADOPTED.              
                                                                  
  MT = 2  ELASTIC SCATTERING                                      
    CALCULATED AS (TOTAL - SUM OF PARTIAL CROSS SECTIONS).        
                                                                  
  MT = 4, 51 - 91  INELASTIC SCATTERING                           
    SPHERICAL OPTICAL AND STATISTICAL MODEL CALCULATION WAS       
    ADOPTED.  THE LEVEL SCHEME WAS TAKEN FROM REF./14/            
                                                                  
           NO.      ENERGY(MEV)    SPIN-PARITY                    
           GR.       0.0            7/2 +                         
            1        0.4560         5/2 +                         
            2        0.8490         3/2 +                         
            3        0.9800         5/2 +                         
            4        1.4900         1/2 +                         
            5        1.8700        11/2 -                         
            6        2.0700         3/2 +                         
            7        2.1500         1/2 +                         
      LEVELS ABOVE 2.3 MEV WERE ASSUMED TO BE OVERLAPPING.        
                                                                  
  MT = 102  CAPTURE                                               
    SPHERICAL OPTICAL AND STATISTICAL MODEL CALCULATION WITH      
    CASTHY WAS ADOPTED.  DIRECT AND SEMI-DIRECT CAPTURE CROSS     
    SECTIONS WERE ESTIMATED ACCORDING TO THE PROCEDURE OF BENZI   
    AND REFFO/15/ AND NORMALIZED TO 1 MILLI-BARN AT 14 MEV.       
                                                                  
    THE GAMMA-RAY STRENGTH FUNCTION (9.13E-05) WAS DETERMINED FROM
    THE SYSTEMATICS OF RADIATION WIDTH (0.125 EV) AND AVERAGE     
    S-WAVE RESONANCE LEVEL SPACING (1370 EV).                     
                                                                  
    NOTE: INTEGRAL CAPTURE CROSS SECTION OF 90(+-25%) MB/16/      
          MEASURED IN CFRMF COULD NOT BE REPRODUCED.  AVERAGE     
          CROSS SECTION CALCULATED FROM PRESENT DATA IS 9.7 MB.   
                                                                  
  MT = 16  (N,2N) CROSS SECTION                                   
  MT = 17  (N,3N) CROSS SECTION                                   
  MT = 22  (N,N'A) CROSS SECTION                                  
  MT = 28  (N,N'P) CROSS SECTION                                  
  MT = 32  (N,N'D) CROSS SECTION                                  
  MT = 33  (N,N'T) CROSS SECTION                                  
  MT =103  (N,P) CROSS SECTION                                    
  MT =104  (N,D) CROSS SECTION                                    
  MT =105  (N,T) CROSS SECTION                                    
  MT =107  (N,ALPHA) CROSS SECTION                                
    THESE REACTION CROSS SECTIONS WERE CALCULATED WITH THE        
    PREEQUILIBRIUM AND MULTI-STEP EVAPORATION MODEL CODE PEGASUS. 
                                                                  
    THE KALBACH'S CONSTANT K (= 368.2) WAS ESTIMATED BY THE       
    FORMULA DERIVED FROM KIKUCHI-KAWAI'S FORMALISM/17/ AND LEVEL  
    DENSITY PARAMETERS.                                           
                                                                  
    FINALLY, THE (N,P) AND (N,ALPHA) CROSS SECTIONS WERE          
    NORMALIZED TO THE FOLLOWING VALUES AT 14.5 MEV:               
      (N,P)          1.57  MB (SYSTEMATICS OF FORREST/18/)        
      (N,ALPHA)      0.85  MB (SYSTEMATICS OF FORREST)            
                                                                  
  MT = 251  MU-BAR                                                
    CALCULATED WITH CASTHY.                                       
                                                                  
MF = 4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS               
  LEGENDRE POLYNOMIAL COEFFICIENTS FOR ANGULAR DISTRIBUTIONS ARE  
  GIVEN IN THE CENTER-OF-MASS SYSTEM FOR MT=2 AND DISCRETE INELAS-
  TIC LEVELS, AND IN THE LABORATORY SYSTEM FOR MT=91.  THEY WERE  
  CALCULATED WITH CASTHY.  FOR OTHER REACTIONS, ISOTROPIC DISTRI- 
  BUTIONS IN THE LABORATORY SYSTEM WERE ASSUMED.                  
                                                                  
MF = 5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                
  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS WERE CALCULATED WITH 
  PEGASUS FOR INELASTIC SCATTERING TO OVERLAPPING LEVELS AND FOR  
  OTHER NEUTRON EMITTING REACTIONS.                               
                                                                  
TABLE 1  NEUTRON OPTICAL POTENTIAL PARAMETERS                     
                                                                  
                DEPTH (MEV)       RADIUS(FM)    DIFFUSENESS(FM)   
         ----------------------   ------------  ---------------   
        V  = 46.0-0.25E           R0 = 6.58     A0 = 0.62         
        WI = 0.125E-0.0004E**2    RI = 6.58     AI = 0.62         
        WS = 7.0                  RS = 7.08     AS = 0.35         
        VSO= 7.0                  RSO= 6.58     ASO= 0.62         
  THE FORM OF SURFACE ABSORPTION PART IS DER. WOODS-SAXON TYPE.   
                                                                  
TABLE 2  LEVEL DENSITY PARAMETERS                                 
                                                                  
 NUCLIDE       A(1/MEV)  T(MEV)    C(1/MEV)  EX(MEV)   PAIRING    
 ---------------------------------------------------------------  
 53-I -133     1.559E+01 4.890E-01 7.662E-01 2.691E+00 7.000E-01  
 53-I -134     1.500E+01 5.600E-01 4.764E+00 2.769E+00 0.0        
 53-I -135     1.350E+01 5.500E-01 5.307E-01 2.961E+00 8.500E-01  
 53-I -136     1.450E+01 5.500E-01 3.589E+00 2.460E+00 0.0        
                                                                  
 54-XE-134     1.400E+01 6.300E-01 3.184E-01 5.224E+00 1.820E+00  
 54-XE-135     1.550E+01 5.565E-01 7.506E-01 4.010E+00 1.120E+00  
 54-XE-136     1.400E+01 6.500E-01 3.270E-01 5.679E+00 1.970E+00  
 54-XE-137     1.550E+01 5.565E-01 7.470E-01 4.010E+00 1.120E+00  
                                                                  
 55-CS-135     1.343E+01 6.537E-01 1.831E+00 4.203E+00 7.000E-01  
 55-CS-136     1.400E+01 6.000E-01 4.424E+00 2.967E+00 0.0        
 55-CS-137     1.336E+01 6.200E-01 9.986E-01 3.836E+00 8.500E-01  
 55-CS-138     1.470E+01 5.737E-01 4.715E+00 2.858E+00 0.0        
 ---------------------------------------------------------------  
                                                                  
 SPIN CUTOFF PARAMETERS WERE CALCULATED AS 0.146*SQRT(A)*A**(2/3).
 IN THE CASTHY CALCULATION, SPIN CUTOFF FACTORS AT 0 MEV WERE     
 ASSUMED TO BE 4.571 FOR CS-137 AND 5.0 FOR CS-138.               
                                                                  
REFERENCES                                                        
 1) AOKI, T. ET AL.: PROC. INT. CONF. ON NUCLEAR DATA FOR BASIC   
    AND APPLIED SCIENCE, SANTA FE., VOL. 2, P.1627 (1985).        
 2) KAWAI, M. ET AL.: J. NUCL. SCI. TECHNOL., 29, 195 (1992).     
 3) HARADA, H. ET AL.: "PROC. THE 1990 SYMPOSIUM ON NUCL. DATA",  
    JAERI-M 91-032, P.199 (1991).                                 
 4) IGARASI, S. AND FUKAHORI, T.: JAERI 1321 (1991).              
 5) IIJIMA, S. ET AL.: JAERI-M 87-025, P. 337 (1987).             
 6) IGARASI, S. ET AL.: JAERI-M 5752 (1974).                      
 7) PEREY, F.G: PHYS. REV. 131, 745 (1963).                       
 8) HUIZENGA, J.R. AND IGO, G.: NUCL. PHYS. 29, 462 (1962).       
 9) LOHR, J.M. AND HAEBERLI, W.: NUCL. PHYS. A232, 381 (1974).    
10) BECCHETTI, F.D., JR. AND GREENLEES, G.W.: POLARIZATION        
    PHENOMENA IN NUCLEAR REACTIONS ((EDS) H.H. BARSHALL AND       
    W. HAEBERLI), P. 682, THE UNIVERSITY OF WISCONSIN PRESS.      
    (1971).                                                       
11) GILBERT, A. AND CAMERON, A.G.W.: CAN. J. PHYS., 43, 1446      
    (1965).                                                       
12) IIJIMA, S., ET AL.: J. NUCL. SCI. TECHNOL. 21, 10 (1984).     
13) GRUPPELAAR, H.: ECN-13 (1977).                                
14) LEDERER, C.M., ET AL.: "TABLE OF ISOTOPES, 7TH ED.", WILEY-   
    INTERSCIENCE PUBLICATION (1978).                              
15) BENZI, V. AND REFFO, G.: CCDN-NW/10 (1969).                   
16) HARKER, Y.D. AND ANDERL, R.A.: "PROC. SPECIALISTS' MEETING ON 
    NEUTRON CROSS SECTIONS OF FISSION PRODUCT NUCLEI", BOLOGNA,   
    DEC. 12-14, 1979, NEANDC(E)209L, P.5 (1979).                  
17) KIKUCHI, K. AND KAWAI, M.: "NUCLEAR MATTER AND NUCLEAR        
    REACTIONS", NORTH HOLLAND (1968).                             
18) FORREST, R.A.: AERE-R 12419 (1986).