38-Sr- 88

 38-SR- 88 JNDC       EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.        
                      DIST-MAR02 REV3-FEB02            20020222   
----JENDL-3.3         MATERIAL 3837                               
-----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/.                       
93-10 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 300 KEV        
      RESOLVED RESONANCE PARAMETERS FOR JENDL-3 WERE TAKEN FROM   
    JENDL-2 WHICH WAS EVALUATED ON THE BASIS OF THE MEASUREMENTS  
    BILPUCH ET AL./3/, CAMARDA ET AL./4/, MALAN ET AL./5/ AND     
    BOLDEMAN ET AL./6/.                                           
      FOR JENDL-3, RADIATION WIDTHS OF THE 1ST AND 5TH RESONANCE  
    LEVELS (L=0) AT 2.78 AND 13.8 KEV WERE MODIFIED TO 190 AND 106
    MEV, RESPECTIVELY, SO AS TO REPRODUCE THE THERMAL CAPTURE     
    CROSS SECTION OF 5.8+-0.4 MB GIVEN BY ROY ET AL./7/ SCATTERING
    RADIUS OF 7.1 FM WAS TAKEN FROM MUGHABGHAB ET AL./8/          
      FOR JENDL-3.2, THESE RESONANCE PARAMETERS WERE MODIFIED SO  
    AS TO REPRODUCE THE CAPTURE AREA DATA MEASURED AT ORNL, BY    
    TAKING ACCOUNT OF THE CORRECTION FACTOR (1.0737) ANNOUNCED BY 
    ALLEN ET AL./9/                                               
                                                                  
  NO UNRESOLVED RESONANCE REGION                                  
                                                                  
  CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS)   
                     2200 M/S               RES. INTEG.           
      TOTAL           5.436                    -                  
      ELASTIC         5.431                    -                  
      CAPTURE         0.0058                    0.0633            
                                                                  
MF = 3  NEUTRON CROSS SECTIONS                                    
  BELOW 300 KEV, RESONANCE PARAMETERS WERE GIVEN.                 
  ABOVE 300 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 BY IIJIMA AND KAWAI/12/ TO REPRODUCE A SYSTEMATIC    
  TREND OF THE TOTAL CROSS SECTION.  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             0  +                         
            1        1.8360          2  +                         
            2        2.7341          3  -                         
            3        3.1510          0  +                         
            4        3.2185          2  +                         
            5        3.4865          1  +                         
            6        3.5239          2  +                         
            7        3.5846          5  -                         
            8        3.6344          3  +                         
            9        3.9526          4  +                         
           10        3.9900          3  -                         
           11        4.0355          2  +                         
           12        4.1701          4  -                         
           13        4.2240          3  +                         
           14        4.2320          4  +                         
           15        4.2693          3  -                         
           16        4.2980          4  +                         
           17        4.4137          3  +                         
           18        4.4520          4  +                         
           19        4.4840          0  +                         
           20        4.5139          2  -                         
           21        4.6190          2  +                         
      LEVELS ABOVE 4.636 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 (0.0375E-04) WAS ADJUSTED TO  
    REPRODUCE THE CAPTURE CROSS SECTION OF 2.8 MILLI-BARNS AT 100 
    KEV MEASURED BY MUSGROVE ET AL./22,9/                         
                                                                  
  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 =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 (= 380.2) WAS ESTIMATED BY THE       
    FORMULA DERIVED FROM KIKUCHI-KAWAI'S FORMALISM/23/ 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)         15.00  MB (RECOMMENDED BY FORREST/24/)        
      (N,ALPHA)      4.45  MB (SYSTEMATICS OF FORREST/24/)        
                                                                  
  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 = 5.893    A0 = 0.62         
        WS = 7.0                  RS = 6.393    AS = 0.35         
        VSO= 7.0                  RSO= 5.893    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    
 ---------------------------------------------------------------  
 36-KR- 84     9.970E+00 9.600E-01 4.942E-01 8.590E+00 2.630E+00  
 36-KR- 85     1.024E+01 8.900E-01 1.570E+00 6.261E+00 1.170E+00  
 36-KR- 86     9.052E+00 8.686E-01 2.185E-01 5.874E+00 2.100E+00  
 36-KR- 87     9.400E+00 8.860E-01 8.826E-01 5.481E+00 1.170E+00  
                                                                  
 37-RB- 85     1.190E+01 8.690E-01 2.827E+00 7.561E+00 1.460E+00  
 37-RB- 86     1.002E+01 8.500E-01 3.954E+00 4.312E+00 0.0        
 37-RB- 87     8.806E+00 9.410E-01 1.125E+00 5.465E+00 9.300E-01  
 37-RB- 88     9.801E+00 8.185E-01 2.880E+00 3.704E+00 0.0        
                                                                  
 38-SR- 86     1.120E+01 8.900E-01 5.328E-01 8.599E+00 2.700E+00  
 38-SR- 87     1.030E+01 8.610E-01 1.186E+00 5.938E+00 1.240E+00  
 38-SR- 88     9.160E+00 7.510E-01 8.288E-02 4.550E+00 2.170E+00  
 38-SR- 89     9.380E+00 8.200E-01 5.043E-01 4.642E+00 1.240E+00  
 ---------------------------------------------------------------  
                                                                  
 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 5.839 FOR SR- 88 AND 5.818 FOR SR- 89.             
                                                                  
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) BILPUCH, E.G., ET AL.: ANN. PHYS., 14, 387 (1961).            
 4) CAMARDA, H., ET AL.: NCSAC-31, 40 (1970).                     
 5) MALAN, J.G., ET AL.: ANN. PHYS., 89, 284 (1975).              
 6) BOLDEMAN, J.W., ET AL.: NUCL. PHYS., A269, 397 (1976).        
 7) ROY, ET AL.: CAN. J. CHEM., 36, 731 (1958), THE DATA WAS      
   TAKEN FROM WALKER, W.H.: AECL-3037, PART I (1969).             
 8) MUGHABGHAB, S.F. ET AL.: "NEUTRON CROSS SECTIONS, VOL. I,     
    PART A", ACADEMIC PRESS (1981).                               
 9) ALLEN, B.J., ET AL.: NUCL. SCI. ENG., 82, 230 (1982).         
10) IGARASI, S. AND FUKAHORI, T.: JAERI 1321 (1991).              
11) IIJIMA, S. ET AL.: JAERI-M 87-025, P. 337 (1987).             
12) IIJIMA, S. AND KAWAI, M.: J. NUCL. SCI. TECHNOL., 20, 77      
    (1983).                                                       
13) PEREY, F.G: PHYS. REV. 131, 745 (1963).                       
14) HUIZENGA, J.R. AND IGO, G.: NUCL. PHYS. 29, 462 (1962).       
15) LOHR, J.M. AND HAEBERLI, W.: NUCL. PHYS. A232, 381 (1974).    
16) 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).                                                       
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.: PRIVATE COMMUNICATION (1981).                  
21) BENZI, V. AND REFFO, G.: CCDN-NW/10 (1969).                   
22) MUSGROVE, A.R. DE L., ET AL.: PROC. INT. CONF. ON NEUTRON     
    PHYSICS AND NUCL. DATA FOR REACTORS, HARWELL 1978, 449.       
23) KIKUCHI, K. AND KAWAI, M.: "NUCLEAR MATTER AND NUCLEAR        
    REACTIONS", NORTH HOLLAND (1968).                             
24) FORREST, R.A.: AERE-R 12419 (1986).