43-Tc- 99

 43-TC- 99 JNDC       EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.        
                      DIST-SEP90 REV2-NOV93                       
----JENDL-3.2         MATERIAL 4331                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
84-10 EVALUATION FOR JENDL-2 WAS MADE BY JNDC FPND W.G./1/        
90-03 MODIFICATION FOR JENDL-3 WAS MADE/2/.                       
93-11 JENDL-3.2 WAS MADE BY JNDC FPND W.G.                        
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (2,151)       RESOLVED RESONANCE PARAMETERS                 
     ***********************************************************  
                                                                  
                                                                  
MF = 1  GENERAL INFORMATION                                       
  MT=451 COMMENTS AND DICTIONARY                                  
                                                                  
MF = 2  RESONANCE PARAMETERS                                      
  MT=151 RESOLVED AND UNRESOLVED RESONANCE PARAMETERS             
  RESOLVED RESONANCE REGION (MLBW FORMULA) : BELOW 4.219 KEV      
    RESONANCE PARAMETERS WERE TAKEN FROM JENDL-2 WITH SLIGHT      
    MODIFICATION.                                                 
       EVALUATION FOR JENDL-2 WAS MADE BY KIKUCHI /3/.            
    PARAMETERS OF THE 1ST AND 2ND RESONANCES WERE ADOPTED FROM    
    RECOMMENDED VALUES OF FISCHER ET AL./4/, AND SLIGHTLY         
    ADJUSTED SO AS TO REPRODUCE THE CAPTURE CROSS SECTION OF      
    20+-1 BARNS AT 0.0253 EV AND THE RESONANCE INTEGRAL OF        
    340+-20 BARNS /5/.  PARAMETERS OF LEVELS BETWEEN 40 EV AND    
    1.5 KEV WERE EVALUATED ON THE BASIS OF DATA MEASURED BY       
    ADAMCHUK ET AL.  /6/ AND BY LITTLE AND BLOCK/7/.  IN THE      
    ENERGY RANGE FROM 1.0 TO 2.6 KEV, ARTIFICIAL LEVELS WERE      
    GENERATED WITH STAT /8/ BY ASSUMING D=0.04 EV, S0= 0.17E-4,   
    S1=11.12E-4 AND THE AVERAGE RADIATION WIDTH OF 0.17 EV.  FOR  
    THE RESONANCES OF WHICH ENERGY WAS ONLY MEASURED BY LITTLE    
    AND BLOCK, THEIR PARAMETERS WERE ALSO ESTIMATED WITH STAT.    
    ABOVE 2.66 KEV, EVALUATION WAS BASED ON THE CAPTURE AREAS     
    MEASURED BY MACKLIN /9/.  SCATTERING RADIUS WAS TAKEN FROM    
    THE COMPILATION OF MUGHABGHAB ET AL./5/                       
       FOR JENDL-3, TOTAL SPIN J OF SOME RESONANCES WAS TENTATIVE-
    LY ESTIMATED WITH A RANDOM NUMBER METHOD.  IN THIS PROCEDURE, 
    NEUTRON WIDTHS FOR RESONANCES ABOVE 2.66 KEV WERE DETERMINED  
    TO REPRODUCE THE CAPTURE AREAS MEASURED BY MACKLIN/9/.        
       FOR JENDL-3.2, NEUTRON OR RADIATIVE CAPTURE WIDTHS FOR     
    LEVELS BETWEEN 111 EV AND 754 EV WERE MODIFIED SO AS TO       
    REPRODUCE THE CAPTURE AREA MEASURED BY LITTLE AND BLOCK/7/.   
                                                                  
  UNRESOLVED RESONANCE REGION : 4.219 KEV - 100 KEV               
    UNRESOLVED RESONANCE PARAMETERS WERE ADOPTED FROM JENDL-2.    
    THE PARAMETERS WERE ADJUSTED TO REPRODUCE THE CAPTURE CROSS   
    SECTION MEASURED BY MACKLIN /9/.  THE EFFECTIVE SCATTERING    
    RADIUS WAS OBTAINED FROM FITTING TO THE CALCULATED TOTAL CROSS
    SECTION AT 100 KEV.                                           
                                                                  
  TYPICAL VALUES OF THE PARAMETERS AT 70 KEV:                     
    S0 = 0.414E-4, S1 = 4.241E-4, S2 = 0.488 E-4, SG = 90.4E-4,   
    GG = 0.186 EV, R  = 6.215 FM.                                 
                                                                  
  CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS)   
                     2200 M/S               RES. INTEG.           
      TOTAL          23.063                    -                  
      ELASTIC         3.422                    -                  
      CAPTURE        19.641                   312                 
                                                                  
MF = 3  NEUTRON CROSS SECTIONS                                    
  BELOW 100 KEV, RESONANCE PARAMETERS WERE GIVEN.                 
  ABOVE 100 KEV, THE SPHERICAL OPTICAL AND STATISTICAL MODEL      
  CALCULATION WAS PERFORMED WITH CASTHY/10/, BY TAKING ACCOUNT OF 
  COMPETING REACTIONS, OF WHICH CROSS SECTIONS WERE CALCULATED    
  WITH PEGASUS/11/ STANDING ON A PREEQUILIBRIUM AND MULTI-STEP    
  EVAPORATION MODEL.  THE OMP'S FOR NEUTRON GIVEN IN TABLE 1 WERE 
  DETERMINED TO REPRODUCE A SYSTEMATIC TREND OF THE TOTAL CROSS   
  SECTION BY CHANGING RSO OF IIJIMA-KAWAI POTENTIAL/12/.  THE     
  OMP'S FOR CHARGED PARTICLES ARE AS FOLLOWS:                     
     PROTON   = PEREY/13/                                         
     ALPHA    = HUIZENGA AND IGO/14/                              
     DEUTERON = LOHR AND HAEBERLI/15/                             
     HELIUM-3 AND TRITON = BECCHETTI AND GREENLEES/16/            
  PARAMETERS FOR THE COMPOSITE LEVEL DENSITY FORMULA OF GILBERT   
  AND CAMERON/17/ WERE EVALUATED BY IIJIMA ET AL./18/  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
  /19/.                                                           
                                                                  
  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./20/            
                                                                  
           NO.      ENERGY(MEV)    SPIN-PARITY                    
           GR.       0.0            9/2 +                         
            1        0.1405         7/2 +                         
            2        0.1426         1/2 -                         
            3        0.1811         5/2 +                         
            4        0.5091         3/2 -                         
            5        0.5343         5/2 -                         
            6        0.6254         7/2 +                         
            7        0.6715         5/2 -                         
            8        0.7263        11/2 +                         
            9        0.7616         5/2 +                         
           10        0.7620        13/2 +                         
      LEVELS ABOVE 0.9 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/21/ AND NORMALIZED TO 1 MILLI-BARN AT 14 MEV.       
                                                                  
    THE GAMMA-RAY STRENGTH FUNCTION (8.37E-03) WAS ADJUSTED TO    
    REPRODUCE THE CAPTURE CROSS SECTION OF 380 MILLI-BARNS AT 100 
    KEV MEASURED BY MACKLIN/22/.                                  
                                                                  
  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 =106  (N,HE3) 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 (= 101.5) WAS ESTIMATED BY THE       
    FORMULA DERIVED FROM KIKUCHI-KAWAI'S FORMALISM/23/ AND LEVEL  
    DENSITY PARAMETERS.                                           
                                                                  
    FINALLY, THE (N,2N), (N,P) AND (N,ALPHA) CROSS SECTIONS WERE  
    NORMALIZED TO THE FOLLOWING VALUES AT 14.5 MEV:               
      (N,2N)      1230.00  MB (RECOMMENDED BY BYCHKOV ET AL./24/) 
      (N,P)         14.00  MB (RECOMMENDED BY FORREST/25/)        
      (N,ALPHA)      7.00  MB (RECOMMENDED BY 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  = 47.5                 R0 = 5.972    A0 = 0.62         
        WS = 9.74                 RS = 6.594    AS = 0.35         
        VSO= 7.0                  RSO= 5.97     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    
 ---------------------------------------------------------------  
 41-NB- 95     1.277E+01 7.500E-01 2.121E+00 5.782E+00 1.120E+00  
 41-NB- 96     1.331E+01 5.880E-01 3.406E+00 2.530E+00 0.0        
 41-NB- 97     1.337E+01 6.710E-01 9.771E-01 5.026E+00 1.290E+00  
 41-NB- 98     1.380E+01 5.110E-01 2.350E+00 1.731E+00 0.0        
                                                                  
 42-MO- 96     1.403E+01 7.410E-01 6.991E-01 7.645E+00 2.400E+00  
 42-MO- 97     1.517E+01 6.800E-01 2.769E+00 6.036E+00 1.280E+00  
 42-MO- 98     1.594E+01 6.900E-01 7.358E-01 7.888E+00 2.570E+00  
 42-MO- 99     1.774E+01 6.200E-01 4.294E+00 6.058E+00 1.280E+00  
                                                                  
 43-TC- 97     1.600E+01 6.700E-01 4.756E+00 6.089E+00 1.120E+00  
 43-TC- 98     1.659E+01 6.120E-01 1.776E+01 4.176E+00 0.0        
 43-TC- 99     1.600E+01 6.550E-01 2.973E+00 5.984E+00 1.290E+00  
 43-TC-100     1.637E+01 5.850E-01 1.189E+01 3.635E+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 7.899 FOR TC- 99 AND 5.0 FOR TC-100.               
                                                                  
REFERENCES                                                        
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    AND APPLIED SCIENCE, SANTA FE., VOL. 2, P.1627 (1985).        
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 3) KIKUCHI, Y. ET AL.: JAERI-M 86-030 (1986).                    
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    NUCL. DATA FOR REACTORS AND OTHER APPLIED PURPOSES, HARWELL   
    1978", 718.                                                   
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    PART A", ACADEMIC PRESS (1981).                               
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    (1977).                                                       
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    (1983).                                                       
13) PEREY, F.G: PHYS. REV. 131, 745 (1963).                       
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15) LOHR, J.M. AND HAEBERLI, W.: NUCL. PHYS. A232, 381 (1974).    
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    (1971).                                                       
17) GILBERT, A. AND CAMERON, A.G.W.: CAN. J. PHYS., 43, 1446      
    (1965).                                                       
18) IIJIMA, S., ET AL.: J. NUCL. SCI. TECHNOL. 21, 10 (1984).     
19) GRUPPELAAR, H.: ECN-13 (1977).                                
20) MATSUMOTO, J., ET AL.: JAERI-M 7734 (1978).                   
21) BENZI, V. AND REFFO, G.: CCDN-NW/10 (1969).                   
22) MACKLIN, R.L.: NUCL. SCI. ENG., 81, 520 (1982).               
23) KIKUCHI, K. AND KAWAI, M.: "NUCLEAR MATTER AND NUCLEAR        
    REACTIONS", NORTH HOLLAND (1968).                             
24) BYCHKOV, V.M. ET AL.: INDC(CCP)-146/LJ (1980).                
25) FORREST, R.A.: AERE-R 12419 (1986).