47-Ag-107

 47-AG-107 JAERI      EVAL-MAR87 LIU T.J.,T.NAKAGAWA.,K.SHIBATA   
                      DIST-SEP89 REV2-FEB94                       
----JENDL-3.2         MATERIAL 4725                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
87-03 NEW EVALUATION FOR JENDL-3/1/                               
87-07 COMPILED BY K.SHIBATA                                       
94-02 JENDL-3.2 WAS MADE BY JNDC FPND W.G.                        
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (2,151)       RESOLVED RESONANCE PARAMETERS                 
      (3,2), (3,3), (3,4), (3,51-54), (3,56-59), (3,61-66)        
                    CURVES OF INELASTIC SCATTERING CROSS SECTIONS 
                    WERE SMOOTHED BY ADDING INTERPOLATED VALUES AT
                    SEVERAL ENERGY POINTS.                        
     ***********************************************************  
                                                                  
                                                                  
MF=1  GENERAL INFORMATION                                         
  MT=451 COMMENTS AND DICTIONARY                                  
                                                                  
MF=2  RESONANCE PARAMETERS                                        
  MT=151                                                          
  RESOLVED RESONANCE PARAMETERS (BELOW 7.0095 KEV)                
       RESOLVED RESONANCE PARAMETERS (BELOW 7.0095KEV) FOR        
    JENDL-3.1 ARE THE SAME AS THOSE OF JENDL-2, WHICH WERE MADE BY
    NAKAJIMA /2/ ON THE BASIS OF EXPERIMENTAL DATA BY MOXON AND   
    RAE /3/, GARG ET AL./4/, ASGHAR ET AL./5/, MURADJAN AND       
    ADAMCHUK /6/, DE BARROS ET AL./7/, PATTENDEN AND JOLLY /8/,   
    MACKLIN /9/ AND MIZUMOTO ET AL./10/.  THERE WERE NO NEW       
    EXPERIMENTAL DATA AVAILABLE SINCE JENDL-2 EVALUATION.  ONLY   
    TOTAL SPIN J AND ANGULAR MOMENTUM L OF SOME RESONANCES WAS    
    ESTIMATED WITH A RANDOM NUMBER METHOD AND A METHOD OF         
    BOLLINGER AND THOMAS/11/, RESPECTIVELY.                       
      THE CAPTURE CROSS SECTION OF JENDL-3.1 BETWEEN 1.3 AND 2.6  
    KEV IS TOO LOW COMPARED WITH INTERPOLATED VALUES FROM THE     
    LOWER AND HIGHER ENERGY REGIONS.  TO COMPENSATE THE LOWER     
    CAPTURE CROSS SECTION, P-WAVE RESONANCES WITH A CAPTURE AREA  
    OF 0.04 EV WERE ADDED EVERY 40 EV BETWEEN 1.28 AND 2.04 KEV,  
    AND EVERY 15 EV BETWEEN 2.04 AND 2.64 KEV.  THE OTHER DATA ARE
    THE SAME AS JENDL-3.1, EXCEPT FOR NEUTRON WIDTH WHICH WAS     
    MODIFIED SO AS TO REPRODUCE THE CAPTURE AREA MEASURED BY      
    MACKLIN/9/.                                                   
                                                                  
  UNRESOLVED RESONANCE PARAMETERS (7.0095 - 100 KEV)              
    THE PARAMETERS WERE DETERMINED WITH THE ASREP CODE /12/ TO    
    REPRODUCE THE CAPTURE AND TOTAL CROSS SECTIONS, WHICH WERE    
    BASED ON EXPERIMENTAL DATA /13, 14/ AND ADJUSTED FOR          
    CONSISTENCE BETWEEN THE DATA OF THE NATURAL ELEMENT AND ITS   
    ISOTOPES. THE TYPICAL PARAMETERS ARE :                        
                                                                  
      S0 = (0.344-0.516)E-4,  S1 = (3.5-4.5)E-4,  S2= 0.53E-4,    
      D-OBS= (18.5-22.8)EV,   R=6.54FM                            
                                                                  
  CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS):  
                     2200 M/S               RES. INTEG.           
      TOTAL          46.310                    -                  
      ELASTIC         7.687                    -                  
      CAPTURE        38.623                   104                 
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
                                                                  
 MT=1,102  TOTAL, CAPTURE                                         
  BELOW 100 KEV, RESONANCE PARAMETERS WERE GIVEN.  NO BACKGROUND  
  CROSS SECTIONS ARE ADOPTED.  ABOVE 100 KEV, CROSS SECTIONS WERE 
  EVALUATED ON THE BASIS OF EXPERIMENTAL DATA AND THEORETICAL     
  CALCULATIONS.  THE MAIN DATA WERE TAKEN FROM THE WORKS OF       
  DUKEREVICH ET AL. /15/, SMITH ET AL. /16/ FOR TOTAL CROSS       
  SECTOIN AND MIZUMOTO ET AL. /12/, MACKLIN ET AL. /9/ FOR CAPTURE
  CROSS SECTION. THE DATA WERE FITTED WITH SPLINE FUNCTION        
  /17/,AND WERE ADJUSTED FOR CONSISTENCE BETWEEN THE NATURAL      
  ELEMENT AND ITS ISOTOPES.                                       
 MT=2  ELASTIC                                                    
  ELASTIC = TOTAL - NONELASTIC                                    
 MT=3  NONELASTIC                                                 
  SUM OF MT=4,16,17,22,28,102,103,107                             
 MT=4  TOTAL INELASTIC                                            
  SUM OF MT=51-66,91                                              
 MT=16,17,22,28,51-66,91,103,107  (N,2N),(N,3N),(N,NA),(N,NP),    
 INELASTIC,(N,P),(N,A)                                            
  FOR THESE REACTIONS THE CROSS SECTIONS WERE CALCULATED WITH THE 
  MULTI-STEP HAUSER-FESHBACH CODE TNG /18, 19/.  AT FIRST, THE    
  OPTICAL MODEL AND LEVEL DENSITY PARAMETERS WERE TAKEN FROM THE  
  WORKS OF SMITH ET AL./20/ AND IIJIMA ET AL./21/, RESPECTIVELY   
  AND THEN THEY WERE ADJUSTED TO REPRODUCE THE AVAILABLE          
  EXPERIMENTAL DATA.                                              
                                                                  
      FOR JENDL-3.2, INELASTIC SCATTERING CROSS SECTIONS AT       
      THRESHOLD ENERGIES OF OTHER LEVELS WERE INSERTED BY         
      INTERPOLATING THE CALUCULATED VALUES WITH AKIMA'S METHOD.   
                                                                  
  THE OPTICAL MODEL PARAMETERS ARE:                               
                                                                  
               DEPTH (MEV)       RADIUS(FM)   DIFFUSENESS(FM)     
            -----------------   ------------  ---------------     
    NEUTRON V  = 48.25-0.3E      R0 = 1.249    A0 = 0.603         
            WS = 8.501-0.15E     RS = 1.270    AS = 0.575         
            VSO= 6.000           RSO= 1.249    ASO= 0.603         
    PROTON  V  = 66.061-0.550E   R0 = 1.150    A0 = 0.650         
            WS = 12.50-0.10E     RS = 1.250    AS = 0.470         
                                 RC = 1.150                       
    ALPHA   V  = 193.0-0.15E     R0 = 1.370    A0 = 0.560         
            WS = 21.00+0.25E     RS = 1.370    AS = 0.560         
                                 RC = 1.370                       
                                                                  
 THE LEVEL DENSITY PARAMETERS ARE:                                
                                                                  
         ECUT(MEV) EJO(MEV) T(MEV) A(1/MEV) C(MEV) CSPIN   EPAIR  
  RH-103   0.990    5.409   0.655    15.50  3.884  49.725  0.94   
  RH-104   0.230    4.351   0.650    15.43  17.72  49.820  0.00   
  PD-106   2.380    8.004   0.666    17.17  0.920  56.147  2.59   
  PD-107   0.700    7.693   0.769    14.98  6.956  49.293  1.35   
  AG-105   1.230    5.830   0.609    18.57  2.750  60.343  0.94   
  AG-106   0.400    3.549   0.563    17.16  12.92  56.110  0.00   
  AG-107   1.420    5.918   0.693    14.55  2.412  47.878  1.24   
  AG-108   0.270    3.014   0.576    15.04  6.004  49.799  0.00   
                                                                  
 THE LEVEL SCHEME IS GIVEN AS FOLLOWS:                            
                                                                  
           NO.      ENERGY(MEV)    SPIN-PARITY                    
           GR.       0.0            1/2 -                         
            1        0.0930         7/2 +                         
            2        0.1260        (9/2)+                         
            3        0.3250         3/2 -                         
            4        0.4230         5/2 -                         
            5        0.7730       (11/2)+                         
            6        0.7870         3/2 -                         
            7        0.9220         5/2 +                         
            8        0.9500         5/2 -                         
            9        0.9730        (7/2)-                         
           10        0.9910       (13/2)+                         
           11        1.0610        (1/2 -)                        
           12        1.1420         1/2 +                         
           13        1.1470         7/2 -                         
           14        1.2230         5/2 +                         
           15        1.2590        (3/2)+                         
           16        1.3260        (3/2)+                         
   CONTINUUM LEVELS WERE ASSUMED ABOVE 1.42 MEV.                  
                                                                  
 MT=251                                                           
  CALCULATED FROM MF=4,MT=2.                                      
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
 MT=2                                                             
  CALCULATED WITH THE CASTHY CODE /22/.                           
 MT=51-66                                                         
  CALCULATED WITH THE TNG CODE.                                   
 MT=16,17,22,28,91                                                
  ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM.               
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
 MT=16,17,22,28,91                                                
  CALCULATED WITH TNG.                                            
                                                                  
MF=12,14,15  GAMMA-PRODUCTION DATA                                
 MT=4,16,17,22,28,102,103,107                                     
  CALCULATED WITH TNG.                                            
                                                                  
REFERENCES                                                        
 1) LIU., T. ET AL.: JAERI-M 91-011 (1991).                       
 2) NAKAJIMA, Y., TO BE PUBLISHED.                                
 3) MOXON, M.C., RAE, E.R., "PROC. EANDC CONF. ON TIME-OF-FLIGHT  
    METHODS, SACLAY, 1961",439.                                   
 4) GARG, J.B., ET AL., PHYS. REV., B137, 547(1965).              
 5) ASGHAR, M., ET AL., "PROC. INT. CONF. ON THE STUDY OF NUCLEAR 
    STRUCTURE WITH NEUTRONS, ANTWERP 1965",(65).                  
 6) MURADJAN, G.V., ADAMCHUK, JU. V., JADERNO-FIZICHESKIE         
    ISSLEDOVANIJA, 6, 64 (1968).                                  
 7) DE BARROS, S., ET AL., NUCL. PHYS., A131, 305(1969).          
 8) PATTENDEN, N.J., JOLLY, J.E., AERE-PR/NP-16(1969).            
 9) MACKLIN, R.L., NUCL. SCI. ENG., 82, 400(1982).                
10) MIZUMOTO, M., ET AL., J. NUCL. SCI. TECHNOL., 20, 883(1983).  
11) BOLLINGER, L.M. AND THOMAS, G.E.: PHYS. REV., 171,1293(1968). 
12) KIKUCHI, Y., PRIVATE COMMUNICATION.                           
13) POENITZ, W.P., WHALEN, J.F., ANL-NDM-80(1983).                
14) MIZUMOTO, M., ET AL., "PROC. INT. CONF. ON NUCL. DATA FOR     
    SCIENCE. AND TECHNOLOGY", ANTWERP, P.226 (1982).              
15) DUKAREVICH, JU.V., ET AL., NUCL. PHYS., A92, 433( 1967).      
16) SMITH, A., ET AL., NUCL. PHYS., A332, 297 (1979).             
17) NAKAGAWA, T., J. AT. ENE. SOC. JAPAN, 22, 559 (1980).         
18) FU, C.Y., ORNL/TM-7042(1980).                                 
19) SHIBATA, K., FU, C.Y., ORNL/TM-10093(1986).                   
20) SMITH, A., ET AL., NUCL. PHYS., A415, 1 (1984).               
21) IIJIMA, S., ET AL.,  J. NUCL. SCI. TECHNOL., 21, 10 (1984).   
22) IGARASI, S. AND FUKAHORI, T.: JAERI 1321 (1991).