35-Br- 81

 35-BR- 81 JNDC       EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.        
                      DIST-MAR02 REV3-FEB02            20020222   
----JENDL-3.3         MATERIAL 3531                               
-----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                                                           
90-03 NEW EVALUATION FOR JENDL-3 WAS COMPLETED BY JNDC FPND       
      W.G./1/                                                     
93-03 JENDL-3.2 WAS MADE BY JNDC FPND W.G.                        
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (2,151)       UNRESOLVED RESONANCE PARAMETERS RE-ADJUSTED   
                    SO AS TO REPRODUCE THE RE-NORMALIZED CAPTURE  
                    CROSS SECTION.                                
      (3,102)       RE-NORMALIZED.                                
      (3,4), (3,51-91) AND ANGULAR DISTRIBUTIONS                  
                    SMALL EFFECTS OF THE RE-NORMALIZATION OF THE  
                    CAPTURE CROSS SECTION.                        
     ***********************************************************  
                                                                  
                                                                  
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 13 KEV         
    RESONANCE ENERGIES FOR THE 304 LEVELS AND FOR THE REMAINING 3 
    LEVELS WERE BASED ON THE MEASUREMENTS BY MACKLIN/2/ AND BY    
    OHKUBO ET AL./3/, RESPECTIVELY.  NEUTRON AND RADIATION WIDTHS 
    WERE DETERMINED BY DIFFERENT METHODS ACCORDING TO THE         
    FOLLOWING THREE CONDITIONS, RESPECTIVELY.                     
                                                                  
    1) IN CASES WHERE TOTAL WIDTH AND NEUTRON CAPTURE AREA        
    MEASURED BY MACKLIN WERE GIVEN FOR A RESONANCE LEVEL, THE     
    NEUTRON AND RADIATION WIDTHS WERE SIMULTANEOUSLY OBTAINED BY  
    SOLVING A QUADRATIC EQUATION.                                 
                                                                  
    2) IN CASES WHERE NEUTRON CAPTURE AREA MEASURED BY MACKLIN AND
    G*(REDUCED NEUTRON WIDTH) MEASURED BY OHKUBO ET AL. WERE      
    AVAILABLE, THE RADIATION WIDTHS WERE DERIVED FROM THE BOTH    
    DATA.                                                         
                                                                  
    3) IN CASES WHERE ONLY NEUTRON CAPTURE AREA BY MACKLIN WAS    
    AVAILABLE, OR G*(NEUTRON WIDTH) BY OHKUBO ET AL. WAS SMALLER  
    THAN NEUTRON CAPTURE AREA BY MACKLIN FOR A RESONANCE LEVEL,   
    THE AVERAGE RADIATION WIDTH OF 279 MEV GIVEN BY MACKLIN WAS   
    ADOPTED.  THE NEUTRON WIDTH WAS DERIVED FROM THIS AVERAGE     
    RADIATION WIDTH AND THE NEUTRON CAPTURE AREA.  IN ADDITION,   
    IF THE VALUE OF G*(AVERAGED RADIATION WIDTH) WAS SMALLER THAN 
    NEUTRON CAPTURE AREA FOR SOME RESONANCE LEVELS, THE AVERAGE   
    RADIATION WIDTH WAS INCREASED DEPENDING ON THE VALUE OF       
    NEUTRON CAPTURE AREA, SO AS TO SATISFY THE FOLLOWING CONDI-   
    TION:                                                         
                                                                  
        G*(AVERAGE RADIATION WIDTH) > NEUTRON CAPTURE AREA.       
                                                                  
    TOTAL SPIN J OF SOME RESONANCES WAS TENTATIVELY ESTIMATED     
    WITH A RANDOM NUMBER METHOD.  NEUTRON ORBITAL ANGULAR         
    MOMENTUM L WAS ASSUMED TO BE 0 FOR ALL RESONANCE LEVELS.      
    SCATTERING RADIUS WAS TAKEN FROM THE GRAPH (FIG. 1, PART A)   
    GIVEN BY MUGHABGHAB ET AL./4/  A NEGATIVE RESONANCE WAS       
    ADDED SO AS TO REPRODUCE THE THERMAL CAPTURE CROSS SECTION    
    GIVEN BY MUGHABGHAB ET AL.                                    
                                                                  
  UNRESOLVED RESONANCE REGION : 13 KEV - 100 KEV                  
    THE NEUTRON STRENGTH FUNCTION S0 WAS BASED ON THE COMPILATION 
    OF MUGHABGHAB ET AL., AND S1 WAS BASED ON THE SYSTEMATICS OF  
    MUGHABGHAB ET AL., AND S2 WAS CALCULATED WITH OPTICAL MODEL   
    CODE CASTHY/5/.  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 WAS BASED ON THE COMPILATION OF MUGHABGHAB ET AL.       
                                                                  
  TYPICAL VALUES OF THE PARAMETERS AT 70 KEV:                     
    S0 = 0.800E-4, S1 = 2.000E-4, S2 = 0.690E-4, SG = 17.3E-4,    
    GG = 0.300 EV, R  = 7.334 FM.                                 
                                                                  
  CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS)   
                     2200 M/S               RES. INTEG.           
      TOTAL           6.307                    -                  
      ELASTIC         3.616                    -                  
      CAPTURE         2.690                    46.7               
                                                                  
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, BY TAKING ACCOUNT OF     
  COMPETING REACTIONS, OF WHICH CROSS SECTIONS WERE CALCULATED    
  WITH PEGASUS/6/ 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 R0, RS AND RSO OF IIJIMA-KAWAI POTENTIAL/7/.
  THE OMP'S FOR CHARGED PARTICLES ARE AS FOLLOWS:                 
     PROTON   = PEREY/8/                                          
     ALPHA    = HUIZENGA AND IGO/9/                               
     DEUTERON = LOHR AND HAEBERLI/10/                             
     HELIUM-3 AND TRITON = BECCHETTI AND GREENLEES/11/            
  PARAMETERS FOR THE COMPOSITE LEVEL DENSITY FORMULA OF GILBERT   
  AND CAMERON/12/ WERE EVALUATED BY IIJIMA ET AL./13/  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
  /14/.                                                           
                                                                  
  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 BASED ON EVALUATED NUCLEAR      
    STRUCTURE DATA FILE (1987 VERSION)/15/ AND NUCLEAR DATA       
    SHEETS/16/.                                                   
                                                                  
           NO.      ENERGY(MEV)    SPIN-PARITY                    
           GR.       0.0            3/2 -                         
            1        0.2760         5/2 -                         
            2        0.5362         9/2 +                         
            3        0.5382         1/2 -                         
            4        0.5660         3/2 -                         
            5        0.6499         3/2 -                         
            6        0.7672         3/2 -                         
            7        0.7925         3/2 +                         
            8        0.8150         1/2 +                         
            9        0.8283         3/2 -                         
           10        0.8324         1/2 -                         
           11        0.8364         7/2 -                         
           12        1.1047         1/2 -                         
           13        1.1899         5/2 -                         
           14        1.2666         3/2 -                         
           15        1.3228         5/2 -                         
           16        1.3275         5/2 -                         
           17        1.3525         1/2 -                         
           18        1.3757         7/2 +                         
           19        1.5428         1/2 -                         
           20        1.5870         1/2 +                         
           21        1.9499         7/2 +                         
           22        1.9852         3/2 +                         
           23        2.0559         1/2 -                         
           24        2.0846         7/2 +                         
           25        2.1225         3/2 +                         
           26        2.1641         1/2 -                         
      LEVELS ABOVE 2.193 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/17/ AND NORMALIZED TO 1 MILLI-BARN AT 14 MEV.       
                                                                  
    THE GAMMA-RAY STRENGTH FUNCTION (1.65E-03) WAS ADJUSTED TO    
    REPRODUCE THE CAPTURE CROSS SECTION OF 119 MILLI-BARNS AT 90  
    KEV MEASURED BY MACKLIN/2/.                                   
                                                                  
  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 (= 120.9) WAS ESTIMATED BY THE       
    FORMULA DERIVED FROM KIKUCHI-KAWAI'S FORMALISM/18/ 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)         21.50  MB (RECOMMENDED BY FORREST/19/)        
      (N,ALPHA)      5.00  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  = 46.0-0.25E           R0 = 5.7      A0 = 0.62         
        WS = 7.0                  RS = 6.2      AS = 0.35         
        VSO= 7.0                  RSO= 5.7      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    
 ---------------------------------------------------------------  
 33-AS- 77     1.300E+01 8.440E-01 4.637E+00 7.951E+00 1.470E+00  
 33-AS- 78     1.150E+01 7.500E-01 5.001E+00 3.894E+00 0.0        
 33-AS- 79     1.290E+01 8.230E-01 3.020E+00 7.585E+00 1.570E+00  
 33-AS- 80     1.150E+01 7.250E-01 4.181E+00 3.535E+00 0.0        
                                                                  
 34-SE- 78     1.287E+01 8.750E-01 1.163E+00 9.882E+00 2.900E+00  
 34-SE- 79     1.412E+01 8.000E-01 5.994E+00 7.842E+00 1.430E+00  
 34-SE- 80     1.334E+01 8.130E-01 6.129E-01 9.136E+00 3.000E+00  
 34-SE- 81     1.368E+01 7.490E-01 2.463E+00 6.614E+00 1.430E+00  
                                                                  
 35-BR- 79     1.293E+01 8.690E-01 5.790E+00 8.381E+00 1.470E+00  
 35-BR- 80     1.318E+01 7.950E-01 1.882E+01 5.695E+00 0.0        
 35-BR- 81     1.290E+01 8.310E-01 3.275E+00 7.733E+00 1.570E+00  
 35-BR- 82     1.266E+01 6.900E-01 5.789E+00 3.665E+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 3.192 FOR BR- 81 AND 5.0 FOR BR- 82.               
                                                                  
REFERENCES                                                        
 1) KAWAI, M. ET AL.: J. NUCL. SCI. TECHNOL., 29, 195 (1992).     
 2) MACKLIN, R.L.: NUCL. SCI. ENG., 99, 133 (1988).               
 3) OHKUBO, M., KAWARASAKI, Y., AND MIZUMOTO, M.:                 
                              NUCL. SCI. TECH. 18, 745 (1981).    
 4) MUGHABGHAB, S.F. ET AL.: "NEUTRON CROSS SECTIONS, VOL. I,     
    PART A", ACADEMIC PRESS (1981).                               
 5) IGARASI, S.: J. NUCL. SCI. TECHNOL., 12, 67 (1975).           
 6) IIJIMA, S. ET AL.: JAERI-M 87-025, P. 337 (1987).             
 7) IIJIMA, S. AND KAWAI, M.: J. NUCL. SCI. TECHNOL., 20, 77      
    (1983).                                                       
 8) PEREY, F.G: PHYS. REV. 131, 745 (1963).                       
 9) HUIZENGA, J.R. AND IGO, G.: NUCL. PHYS. 29, 462 (1962).       
10) LOHR, J.M. AND HAEBERLI, W.: NUCL. PHYS. A232, 381 (1974).    
11) 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).                                                       
12) GILBERT, A. AND CAMERON, A.G.W.: CAN. J. PHYS., 43, 1446      
    (1965).                                                       
13) IIJIMA, S., ET AL.: J. NUCL. SCI. TECHNOL. 21, 10 (1984).     
14) GRUPPELAAR, H.: ECN-13 (1977).                                
15) ENSDF: EVALUATED NUCLEAR STRUCTURE DATA FILE (JUNE 1987).     
16) NUCLEAR DATA SHEETS, 46, 487 (1985).                          
17) BENZI, V. AND REFFO, G.: CCDN-NW/10 (1969).                   
18) KIKUCHI, K. AND KAWAI, M.: "NUCLEAR MATTER AND NUCLEAR        
    REACTIONS", NORTH HOLLAND (1968).                             
19) FORREST, R.A.: AERE-R 12419 (1986).