40-Zr- 91

 40-ZR- 91 JNDC       EVAL-AUG89 JNDC FP NUCLEAR DATA W.G.        
                      DIST-OCT89 REV2-SEP93                       
----JENDL-3.2         MATERIAL 4028                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
84-10 EVALUATION FOR JENDL-2 WAS MADE BY JNDC FPND W.G./1/        
89-08 MODIFICATION FOR JENDL-3 WAS MADE/2/.                       
90-10 MF=5: SPECTRA AT THRESHOLD ENERGIES WERE MODIFIED.          
93-09 JENDL-3.2.                                                  
      COMPILED BY T.NAKAGAWA (NDC/JAERI)                          
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      ALMOST ALL CROSS SECTION DATA EXCEPT (3,1), (3,102),        
      (3,103) AND (3,107):                                        
          (3,4), (3,51-91), (3,16), (3,17), (3,22), (3,28),       
          (3,32), (3,104), (3,105), (3,106)                       
      (4,16-91)                                                   
      (5,16-91)                                                   
             THESE DATA WERE TAKEN FROM JENDL FUSION FILE.        
     ***********************************************************  
                                                                  
     -------------------------------------------------------------
      JENDL FUSION FILE /3/  (AS OF SEP. 1993)                    
            EVALUATED AND COMILED BY S. CHIBA (NDC/JAERI)         
                                                                  
      DATA WERE TAKEN FROM JENDL-3.1 EXCEPT FOR THE FOLLOWING:    
      -  THE DISCRETE AND CONTINUUM INELASTIC SCATTERING CROSS    
         SECTIONS WERE CALCULATED WITH CASTHY2Y AND DWUCKY IN     
         SINCROS-II SYSTEM/4/ INCLUDING CONTRIBUTIONS FROM        
         DIRECT REACTIONS.                                        
      -  ANGULAR DISTRIBUTIONS OF DISCRETE INELASTICS WERE ALSO   
         CALCULATED WITH CASTHY2Y AND DWUCKY.                     
      -  THRESHOLD REACTION CROSS SECTIONS (MT=16, 17, 22, 28, 32,
         104, 105 AND 106) WERE REPLACED WITH THOSE CALCULATED BY 
         EGNASH2 IN THE SINCROS-II.                               
      -  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS WERE REPLACED 
         BY THOSE CALCULATED BY EGNASH2.  THE DDX'S OF THE CONTI- 
         NUUM NEUTRONS WERE CALCULATED BY KUMABE'S SYSTEMATICS/5/ 
         USING F15TOB /3/.  THE PRECOMPOUND/COMPOUND RATIO WAS    
         CALCULATED BY THE SINCROS- II CODE SYSTEM.               
      -  OPTICAL-MODEL, LEVEL DENSITY AND OTHER PARAMETERS USED IN
         THE SINCROS-II CALCULATION ARE DESCRIBED IN REF./4/.     
         LEVEL SCHEMES WERE DETERMINED ON THE BASIS OF ENSDF/6/.  
     -------------------------------------------------------------
                                                                  
                                                                  
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 30.16 KEV      
    FOR JENDL-2, RESONANCE ENERGIES RECOMMENDED BY MUGHABGHAB ET  
    AL. /7/ WERE ADOPTED.  NEUTRON AND RADIATIVE CAPTURE WIDTHS   
    WERE OBTAINED BY AVERAGING THE DATA OF MUSGROVE ET AL. /8/    
    AND OF BRUSEGAN ET AL. /9/.  FOR THE LEVELS ABOVE 20 KEV,     
    CAPTURE AREAS BY BOLDEMAN ET AL. /10/ WERE ALSO TAKEN INTO    
    ACCOUNT.  PARAMETERS OF A NEGATIVE RESONANCE WERE ADOPTED     
    FROM REF./7/.  THE EFFECTIVE SCATTERING RADIUS WAS ALSO TAKEN 
    FROM REF./7/.                                                 
      ASSUMED CAPTURE WIDTH = 0.120 EV FOR S-WAVE RES.            
                              0.240 EV FOR P-WAVE RES.            
    FOR JENDL-3, THUS EVALUATED PARAMETERS WERE MODIFIED BY TAKING
    ACCOUNT OF THE EVALUATION BY COCEVA/11/.  AFTER MODIFICATION, 
    RADIATIVE WIDTHS WERE DETERMINED SO AS TO REPRODUCE CAPTURE   
    AREAS OF JENDL-2.                                             
  UNRESOLVED RESONANCE REGION : 30.16 KEV - 100 KEV               
    THE NEUTRON STRENGTH FUNCTIONS, S0, S1 AND S2 WERE CALCULATED 
    WITH OPTICAL MODEL CODE CASTHY/12/.  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.                                                   
                                                                  
  TYPICAL VALUES OF THE PARAMETERS AT 70 KEV:                     
    S0 = 0.420E-4, S1 = 5.700E-4, S2 = 0.360E-4, GG = 0.205 EV    
    DO = 660.4 EV, R  = 6.621 FM.                                 
                                                                  
  CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS)   
                     2200 M/S               RES. INTEG.           
      TOTAL          11.83                     -                  
      ELASTIC        10.59                     -                  
      CAPTURE         1.247                     6.95              
                                                                  
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/12/, BY TAKING ACCOUNT OF 
  COMPETING REACTIONS, OF WHICH CROSS SECTIONS WERE CALCULATED    
  WITH PEGASUS/13/ STANDING ON A PREEQUILIBRIUM AND MULTI-STEP    
  EVAPORATION MODEL.  THE OMP'S FOR NEUTRON GIVEN IN TABLE 1 WERE 
  DETERMINED BY IIJIMA AND KAWAI/14/ TO REPRODUCE A SYSTEMATIC    
  TREND OF THE TOTAL CROSS SECTION.  THE OMP'S FOR CHARGED        
  PARTICLES ARE AS FOLLOWS:                                       
     PROTON   = PEREY/15/                                         
     ALPHA    = HUIZENGA AND IGO/16/                              
     DEUTERON = LOHR AND HAEBERLI/17/                             
     HELIUM-3 AND TRITON = BECCHETTI AND GREENLEES/18/            
  PARAMETERS FOR THE COMPOSITE LEVEL DENSITY FORMULA OF GIRBERT   
  AND CAMERON/19/ WERE EVALUATED BY IIJIMA ET AL./20/.  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
  /21/.                                                           
                                                                  
     FOR JENDL-3.2, DATA OF NEUTRON EMITTING REACTIONS WERE       
  ADOPTED FROM JENDL FUSION FILE.  THE CALCULATION WAS MADE WITH  
  SINCROS-II SYSTEM/4/ BY ADOPTING WALTER-GUSS OMP MODIFIED BY    
  YAMAMURO/4/ FOR NEUTRONS, LEMOS OMP MODIFIED BY ARTHUR AND      
  YOUNG/22/ FOR ALPHA, THE SAME OMP'S AS THE PEGASUS CALCULATION  
  FOR OTHER CHARGED PARTICLES AND STANDARD LEVEL DENSITY PARAME-  
  TERS OF SINCROS-II SYSTEM.                                      
                                                                  
  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                           
    TAKEN FROM JENDL FUSION FILE.  THE LEVEL SCHEME WAS TAKEN FROM
    REF./6/  CONTRIBUTIONS OF THE DIRECT PROCESS WAS CALCULATED   
    FOR THE LEVELS MARKED WITH '*'.                               
                                                                  
           NO.      ENERGY(MEV)    SPIN-PARITY (DIRECT PROCESS)   
           GR.       0.0            5/2 +                         
            1        1.2048         1/2 +                         
            2        1.4663         5/2 +          *              
            3        1.8821         7/2 +          *              
            4        2.0422         3/2 +          *              
            5        2.1313         9/2 +          *              
            6        2.1700        11/2 -                         
            7        2.1899         5/2 +                         
            8        2.2007         7/2 +                         
            9        2.2597        13/2 -                         
           10        2.2876        15/2 -                         
           11        2.3201        11/2 -          *              
           12        2.3558         1/2 -          *              
           13        2.3669         7/2 -          *              
           14        2.3949         9/2 -          *              
      LEVELS ABOVE 2.395 MEV WERE ASSUMED TO BE OVERLAPPING.      
                                                                  
  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 =104  (N,D) CROSS SECTION                                    
  MT =105  (N,T) CROSS SECTION                                    
  MT =106  (N,HE3) CROSS SECTION                                  
    DATA WERE ADOPTED FROM JENDL FUSION FILE.                     
                                                                  
  MT = 102  CAPTURE                                               
    SPHERICAL OPTICAL AND STATISTICAL MODEL CALCULATION WITH      
    CASTHY/12/ WAS ADOPTED.  DIRECT AND SEMI-DIRECT CAPTURE CROSS 
    SECTIONS WERE ESTIMATED ACCORDING TO THE PROCEDURE OF BENZI   
    AND REFFO/23/ AND NORMALIZED TO 1 MILLI-BARN AT 14 MEV.       
                                                                  
    THE GAMMA-RAY STRENGTH FUNCTION (3.199E-04) WAS ADJUSTED TO   
    REPRODUCE THE CAPTURE CROSS SECTION OF 25 MILLI-BARNS AT 100  
    KEV MEASURED BY MUSGROVE ET AL./24/                           
                                                                  
  MT =103  (N,P) CROSS SECTION                                    
  MT =107  (N,ALPHA) CROSS SECTION                                
    THESE REACTION CROSS SECTIONS WERE CALCULATED WITH THE        
    PREEQUILIBRIUM AND MULTI-STEP EVAPORATION MODEL CODE          
    PEGASUS/13/.                                                  
                                                                  
    THE KALBACH'S CONSTANT K (=269.1) WAS ESTIMATED BY THE FORMULA
    DERIVED FROM KIKUCHI-KAWAI'S FORMALISM/25/ AND LEVEL DENSITY  
    PARAMETERS.                                                   
                                                                  
    FINALLY, (N,P) AND (N,ALPHA) CROSS SECTIONS WERE NORMALIZED TO
    THE FOLLOWING VALUES AT 14.5 MEV:                             
      (N,P)         29.00  MB (RECOMMENDATION BY FORREST/26/)     
      (N,ALPHA)      8.51  MB (SYSTEMATICS OF BY FORREST/26/)     
                                                                  
  MT = 251  MU-BAR                                                
    CALCULATED WITH CASTHY/12/.                                   
                                                                  
MF = 4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS               
  MT = 2                                                          
    CALCULATED WITH CASTHY/12/.                                   
  MT = 51-54                                                      
    TAKEN FROM JENDL FUSION FILE DATA WHICH WAS CALCULATED WITH   
    CASTHY AND DWUCK/27/ (DWUCKY) IN THE SINCROS-II SYSTEM.       
  MT = 16,17,22,28,32,91                                          
    TRANSFORMED FROM MF=6 DATA (DDX) OF JENDL FUSION FILE.        
                                                                  
MF = 5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                
  MT = 16,17,22,28,32,91                                          
    TRANSFORMED FROM MF=6 DATA (DDX) OF JENDL FUSION FILE.        
                                                                  
                                                                  
================================================================= 
<> 
================================================================= 
                                                                  
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         
        WSO= 7.0                  RSO= 5.893    ASO= 0.62         
                                                                  
TABLE 2  LEVEL DENSITY PARAMETERS                                 
                                                                  
 NUCLIDE       A(/MEV)   T(MEV)    C(/MEV)   EX(MEV)   PAIRING    
 ---------------------------------------------------------------  
 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  
 38-SR- 90     9.940E+00 8.530E-01 3.795E-01 6.252E+00 1.960E+00  
                                                                  
 39-Y - 88     1.109E+01 7.450E-01 3.738E+00 3.570E+00 0.0        
 39-Y - 89     7.900E+00 8.500E-01 3.983E-01 3.440E+00 9.300E-01  
 39-Y - 90     1.027E+01 6.770E-01 1.716E+00 2.209E+00 0.0        
 39-Y - 91     1.050E+01 7.140E-01 8.362E-01 3.521E+00 7.200E-01  
                                                                  
 40-ZR- 89     1.095E+01 8.260E-01 1.379E+00 5.864E+00 1.200E+00  
 40-ZR- 90     9.152E+00 8.222E-01 1.526E-01 5.383E+00 2.130E+00  
 40-ZR- 91     1.036E+01 8.000E-01 7.822E-01 5.057E+00 1.200E+00  
 40-ZR- 92     1.088E+01 8.192E-01 5.122E-01 6.429E+00 1.920E+00  
 ---------------------------------------------------------------  
                                                                  
  SPIN CUTOFF PARAMS WERE CALCULATED AS 0.146*SQRT(A)*A**(2/3).   
  IN THE CASTHY CALCULATION, SPIN CUTOFF FACTORS AT 0 MEV WERE    
  ASSUMED TO BE 12.04 FOR ZR- 91 AND 6.937 FOR ZR- 92.            
                                                                  
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) CHIBA, S. ET AL.: JAERI-M 92-027, P.35 (1992).                
 4) YAMAMURO, N.: JAERI-M 90-006 (1990).                          
 5) KUMABE, I. ET AL.: NUCL. SCI. ENG., 104, 280 (1990).          
 6) ENSDF: EVALUATED NUCLEAR STRUCTURE DATA FILE, BNL/NNDC.       
 7) MUGHABGHAB, S.F. ET AL.: "NEUTRON CROSS SECTIONS, VOL. I,     
    PART A", ACADEMIC PRESS (1981).                               
 8) MUSGROVE, A.R. DE L., ET AL.: AUST, J, PHYS., 30, 391(1977).  
 9) BRUSEGAN, A., ET AL.: "PROC. INT. CONF. ON NEUTRON PHYSICS AND
    NUCL. DATA FOR REACTORS, HARWELL 1978", 706.                  
10) BOLDEMAN, J.W., ET AL.: AAEC/E367 (1976).                     
11) COCEVA, C.: NUCL. SCI. ENG., 91, 209 (1985).                  
12) IGARASI, S. AND FUKAHORI, T.: JAERI 1321 (1991).              
13) IIJIMA, S. ET AL.: JAERI-M 87-025, P. 337 (1987).             
14) IIJIMA, S. AND KAWAI, M.: J. NUCL. SCI. TECHNOL., 20, 77      
    (1983).                                                       
15) PEREY, F.G: PHYS. REV. 131, 745 (1963).                       
16) HUIZENGA, J.R. AND IGO, G.: NUCL. PHYS. 29, 462 (1962).       
17) LOHR, J.M. AND HAEBERLI, W.: NUCL. PHYS. A232, 381 (1974).    
18) 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).                                                       
19) GILBERT, A. AND CAMERON, A.G.W.: CAN. J. PHYS., 43, 1446      
    (1965).                                                       
20) IIJIMA, S., ET AL.: J. NUCL. SCI. TECHNOL. 21, 10 (1984).     
21) GRUPPELAAR, H.: ECN-13 (1977).                                
22) ARTHUR, E.D. AND YOUNG, P.G.: LA-8626-MS (1980).              
23) BENZI, V. AND REFFO, G.: CCDN-NW/10 (1969).                   
24) MUSGROVE, A.R. DE L., ET AL.: "PROC. INT. CONF. ON NEUTRON    
    PHYSICS AND NUCL. DATA FOR REACTORS, HARWELL 1978", 449.      
25) KIKUCHI, K. AND KAWAI, M.: "NUCLEAR MATTER AND NUCLEAR        
    REACTIONS", NORTH HOLLAND (1968).                             
26) FORREST, R.A.: AERE-R 12419 (1986).                           
27) KUNZ, P.D.: PRIVATE COMMUNICATION.