60-Nd-145

 60-ND-145 JNDC       EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.        
                      DIST-MAR02 REV3-FEB02            20020222   
----JENDL-3.3         MATERIAL 6034                               
-----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.                        
94-11 UPPER BOUNDARY OF THE RESOLVED RESONANCE REGION CHANGED     
      FROM 5.10069 KEV TO 4.0 KEV                                 
                                                                  
     *****   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 KEV          
       RESONANCE PARAMETERS WERE TAKEN FROM JENDL-2/3/ WITH       
    MODIFICATION OF TOTAL SPIN J.                                 
       FOR JENDL-2, RESONANCE ENERGIES WERE TAKEN FROM TELLIER    
    /4/, AND AFTER CALIBRATION, DATA OF ROHR ET AL./5/ AND        
    MUSGROVE ET AL./6/ WERE ADOPTED FOR THE LEVELS NOT MEASURED BY
    TELLIER.  NEUTRON WIDTHS WERE ADOPTED FROM TELLIER, AND RADIA-
    TION WIDTHS WERE OBTAINED FROM THE CAPTURE AREAS MEASURED BY  
    ROHR ET AL. AND MUSGROVE ET AL.  THE AVERAGE RADIATION WIDTH  
    OF 0.087 EV WAS ASSUMED FOR THE RESONANCES WHOSE CAPTURE AREA 
    WAS NOT MEASURED, AND TO ESTIMATE NEUTRON WIDTHS FROM THE     
    CAPTURE AREAS FOR THE RESONANCES NOT MEASURED BY TELLIER.  A  
    NEGATIVE RESONANCE WAS ADDED SO AS TO REPRODUCE THE THERMAL   
    CAPTURE AND TOTAL CROSS SECTIONS GIVEN BY MUGHABGHAB ET AL./7/
       FOR JENDL-3, TOTAL SPIN J OF SOME RESONANCES WAS TENTATIVE-
    LY ESTIMATED WITH A RANDOM NUMBER METHOD.                     
       FOR JENDL-3.2, THE CAPTURE DATA MEASURED AT ORELA OF ORNL  
    WERE RENORMALIZED (FACTOR = 0.9507)/8/.  THE NEUTRON WIDTH    
    AND/OR THE RADIATION WIDTH WAS REVISED TO REPRODUCE THE       
    RENORMALIZED CAPTURE AREA FOR EACH RESONANCE ABOVE 2.592 KEV. 
                                                                  
  UNRESOLVED RESONANCE REGION : 4 KEV - 100 KEV                   
    UNRESOLVED RESONANCE PARAMETERS WERE ADOPTED FROM JENDL-2.    
    THE NEUTRON STRENGTH FUNCTIONS, S0, S1 AND S2 WERE CALCULATED 
    WITH OPTICAL MODEL CODE CASTHY/9/.  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 = 2.927E-4, S1 = 0.685E-4, S2 = 3.510E-4, SG = 54.7E-4,    
    GG = 0.0975EV, R  = 7.683 FM.                                 
                                                                  
  CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS)   
                     2200 M/S               RES. INTEG.           
      TOTAL          64.065                    -                  
      ELASTIC        20.222                    -                  
      CAPTURE        43.843                   204                 
     (N,ALPHA)        8.855E-05                 2.03E-3           
                                                                  
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/10/ STANDING ON A PREEQUILIBRIUM AND MULTI-STEP    
  EVAPORATION MODEL.  THE OMP'S FOR NEUTRON GIVEN IN TABLE 1 WERE 
  DETERMINED BY IIJIMA AND KAWAI/11/ TO REPRODUCE A SYSTEMATIC    
  TREND OF THE TOTAL CROSS SECTION.                               
  THE OMP'S FOR CHARGED PARTICLES ARE AS FOLLOWS:                 
     PROTON   = PEREY/12/                                         
     ALPHA    = HUIZENGA AND IGO/13/                              
     DEUTERON = LOHR AND HAEBERLI/14/                             
     HELIUM-3 AND TRITON = BECCHETTI AND GREENLEES/15/            
  PARAMETERS FOR THE COMPOSITE LEVEL DENSITY FORMULA OF GILBERT   
  AND CAMERON/16/ WERE EVALUATED BY IIJIMA ET AL./17/  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
  /18/.                                                           
                                                                  
  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./19/.           
                                                                  
           NO.      ENERGY(MEV)    SPIN-PARITY                    
           GR.       0.0            7/2 -                         
            1        0.0671         3/2 -                         
            2        0.0722         5/2 -                         
            3        0.5066         3/2 -                         
            4        0.6570        11/2 -                         
            5        0.7490         9/2 -                         
            6        0.7804         3/2 -                         
            7        0.8407         3/2 -                         
            8        0.9202         1/2 -                         
            9        0.9371         5/2 -                         
           10        1.0112        11/2 -                         
           11        1.0514         7/2 -                         
           12        1.0852         3/2 +                         
           13        1.1503         9/2 -                         
           14        1.1610         5/2 -                         
           15        1.1620         9/2 -                         
           16        1.2500         5/2 -                         
      LEVELS ABOVE 1.3 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/20/ AND NORMALIZED TO 1 MILLI-BARN AT 14 MEV.       
                                                                  
    THE GAMMA-RAY STRENGTH FUNCTION (5.58E-03) WAS ADJUSTED TO    
    REPRODUCE THE CAPTURE CROSS SECTION OF 510 MILLI-BARNS AT 30  
    KEV MEASURED BY NAKAJIMA ET AL./21/                           
                                                                  
  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 (= 168.3) WAS ESTIMATED BY THE       
    FORMULA DERIVED FROM KIKUCHI-KAWAI'S FORMALISM/22/ 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)          7.50  MB (RECOMMENDED BY FORREST/23/)        
      (N,ALPHA)      2.47  MB (SYSTEMATICS OF FORREST/23/)        
                                                                  
    THE (N,ALPHA) CROSS SECTION BELOW 4 KEV WAS CALCULATED FROM   
    RESONANCE PARAMETERS, BY ASSUMING A MEAN ALPHA WIDTH OF       
    1.50E-7 EV SO AS TO REPRODUCE THE THERMAL CROSS SECTION/7/.   
    THE CROSS SECTION WAS AVERAGED IN SUITABLE ENERGY INTERVALS.  
    ABOVE 4 KEV, THE CROSS SECTION WAS CONNECTED SMOOTHLY TO THE  
    PEGASUS CALCULATION.                                          
                                                                  
  MT = 251  MU-BAR                                                
    CALCULATED WITH CASTHY/9/.                                    
                                                                  
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  = 47.94                R0 = 6.718    A0 = 0.6          
        WS = 9.13                 RS = 7.564    AS = 0.45         
        VSO= 7.0                  RSO= 6.771    ASO= 0.6          
  THE FORM OF SURFACE ABSORPTION PART IS DER. WOODS-SAXON TYPE.   
                                                                  
TABLE 2  LEVEL DENSITY PARAMETERS                                 
                                                                  
 NUCLIDE  SYST A(1/MEV)  T(MEV)    C(1/MEV)  EX(MEV)   PAIRING    
 ---------------------------------------------------------------  
 58-CE-141     1.714E+01 5.150E-01 7.134E-01 3.957E+00 1.170E+00  
 58-CE-142     1.600E+01 6.000E-01 4.210E-01 5.674E+00 1.930E+00  
 58-CE-143     1.900E+01 5.500E-01 2.613E+00 5.094E+00 1.170E+00  
 58-CE-144     1.700E+01 6.000E-01 5.074E-01 6.214E+00 2.090E+00  
                                                                  
 59-PR-142     1.595E+01 6.150E-01 1.201E+01 3.974E+00 0.0        
 59-PR-143     1.500E+01 6.280E-01 2.607E+00 4.558E+00 7.600E-01  
 59-PR-144     1.600E+01 6.000E-01 1.045E+01 3.744E+00 0.0        
 59-PR-145  *  2.088E+01 5.411E-01 7.911E+00 5.258E+00 9.200E-01  
                                                                  
 60-ND-143     1.826E+01 4.710E-01 5.220E-01 3.613E+00 1.180E+00  
 60-ND-144     1.771E+01 5.640E-01 4.792E-01 5.691E+00 1.940E+00  
 60-ND-145     2.054E+01 5.120E-01 2.465E+00 4.869E+00 1.180E+00  
 60-ND-146     2.019E+01 5.660E-01 1.121E+00 6.714E+00 2.100E+00  
 ---------------------------------------------------------------  
  SYST:  * = LDP'S WERE DETERMINED FROM SYSTEMATICS.              
                                                                  
 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 6.875 FOR ND-145 AND 6.125 FOR ND-146.             
                                                                  
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) KIKUCHI, Y. ET AL.: JAERI-M 86-030 (1986).                    
 4) TELLIER, H.: CEA-N-1459 (1971).                               
 5) ROHR, G., ET AL.: "PROC. 3RD CONF. ON NEUTRON CROSS SECTIONS  
    AND TECHNOLOGY, KNOXVILLE 1971", VOL. 2, 743.                 
 6) MUSGROVE, A.R. DE L., ET AL.: AEEC/E401 (1977).               
 7) MUGHABGHAB, S.F.: "NEUTRON CROSS SECTIONS, VOL. I, PART B",   
    ACADEMIC PRESS (1984).                                        
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10) IIJIMA, S. ET AL.: JAERI-M 87-025, P. 337 (1987).             
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    (1983).                                                       
12) PEREY, F.G: PHYS. REV. 131, 745 (1963).                       
13) HUIZENGA, J.R. AND IGO, G.: NUCL. PHYS. 29, 462 (1962).       
14) LOHR, J.M. AND HAEBERLI, W.: NUCL. PHYS. A232, 381 (1974).    
15) 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).                                                       
16) GILBERT, A. AND CAMERON, A.G.W.: CAN. J. PHYS., 43, 1446      
    (1965).                                                       
17) IIJIMA, S., ET AL.: J. NUCL. SCI. TECHNOL. 21, 10 (1984).     
18) GRUPPELAAR, H.: ECN-13 (1977).                                
19) LEDERER, C.M., ET AL.: "TABLE OF ISOTOPES, 7TH ED.", WILEY-   
    INTERSCIENCE PUBLICATION (1978).                              
20) BENZI, V. AND REFFO, G.: CCDN-NW/10 (1969).                   
21) NAKAJIMA, Y., ET AL.: PROC. INT. CONF. ON NEUTRON PHYSICS AND 
    NUCL. DATA FOR REACTORS, HARWELL 1978, 438.                   
22) KIKUCHI, K. AND KAWAI, M.: "NUCLEAR MATTER AND NUCLEAR        
    REACTIONS", NORTH HOLLAND (1968).                             
23) FORREST, R.A.: AERE-R 12419 (1986).