94-Pu-239

 94-PU-239 NAIG       EVAL-MAR87 M.KAWAI, T.YOSHIDA, K.HIDA       
                      DIST-MAR02 REV4-MAR00            20020214   
----JENDL-3.3         MATERIAL 9437                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
87-03 Evaluation was made by                                      
        M.Kawai and K.Hida(naig) :  cross sections above          
                      resonance region and other quantities,      
        T.Yoshida(naig) : resonance parameters and background     
                      cross sections,                             
      Data were compiled by T.Nakagawa (jaeri).                   
88-08 Partly modified.                                            
       Nu-bar, resolved resons., (n,2n).                          
89-02 FP yields were taken from JNDC FP decay data file version-2.
89-03 Unresolved resonance parameters were slightly modified.     
93-02 JENDL-3.2.                                                  
      Resonance parameters evaluated by H.Derrien (jaeri)/1/.     
      Fission spectra calculated by T.Ohsawa (kinki univ.)        
      Compiled by T.Nakagawa (ndc/jaeri)                          
                                                                  
     *****   modified parts for JENDL-3.2   ********************  
      (2,151)       Resolved resonance parameters up to 2.5 keV   
      (5,18)                                                      
     ***********************************************************  
                                                                  
2000-03 JENDL-3.3 compiled by K.Shibata (jaeri)                   
     *****   modified parts for JENDL-3.3   ********************  
      (1,451), (1,455), (2,151), (3,2), (3,18), (3,102),          
      (5,16), (5,17), (5,91), (5,455)                             
     ************************************************************ 
                                                                  
2000-05 Fission spectra were re-evaluated by T.Ohsawa (Kinki U.). 
        JENDL-3.2 was adopted at 14 and 20 MeV.                   
                                                                  
2001-06 Fission spectra were replaced with the calculations by    
        Kawano et al./2/ above 10 MeV.                            
                                                                  
2002-01 Covariances were taken from JENDL-3.2 covariance file     
        except for mf/mt=3/18.                                    
                                                                  
mf=1  General information                                         
  mt=451  Descriptive data and dictionary                         
  mt=452  Number of neutrons per fission                          
     Sum of nu-p (mt=456) and nu-d (mt=455).                      
  mt=455  delayed neutron data                                    
     Evaluated data by Tuttle /3/ were adopted.                   
     Decay constants were adopted from Keepin et al./4/           
  mt=456  Number of prompt neutrons per fission                   
     Standard Cf-252 sf nu-p was taken to be 3.756.  Thermal nu-p 
     was 2.8781 that was a mean value of experimental data.  The  
     energy dependent nu-p was obtained from                      
         below 10 eV      : ref./5/ multiplied by 1.001           
         10 eV  8 MeV            
        Ws   = 3.6 + 0.4*En        (MeV),   En < 7 MeV            
               6.4 + 0.1*(En-7)    (MeV),   En > 7 MeV            
        Vso  = 6.2                 (mev)                          
        r: rv = 1.26 ,  rs= 1.24    rso= 1.12 (fm)                
        a: av = 0.615,  as= 0.50 ,  aso= 0.47 (fm)                
        beta-2= 0.21,  beta-4= 0.065                              
     The compound component was calculated with optical and       
     statistical model code casthy /21/, taking into account      
     level fluctuation and interference effects. The fission,     
     (n,2n), (n,3n), and (n,4n) reactions were considered as      
     competing processes.                                         
                                                                  
     The neutron transmission coefficients for the incident       
     channel were generated with ecis, whereas those for the exit 
     channel were calculated with casthy using spherical optical  
     potential parameters adopted for JENDL-2 evaluation:         
        V  = 40.72 - 0.05*En      (MeV)                           
        Ws = 6.78 - 0.29*En       (MeV)                           
        Vso= 7.0                  (MeV)                           
        r  = rso= 1.32, rs =1.357 (fm)                            
        a  = aso= b = 0.47        (fm)                            
     The surface absorption is of derivative Woods-Saxon type.    
     The level scheme was taken from ref./22/:                    
            no.     energy(keV)   spin-parity coupled level       
            g.s.         0.0         1/2 +        *               
             1           7.86        3/2 +        *               
             2          57.28        5/2 +        *               
             3          75.71        7/2 +        *               
             4         163.76        9/2 +        *               
             5         194.         11/2 +        *               
             6         285.46        5/2 +                        
             7         317.         13/2 +        *               
             8         330.13        7/2 +                        
             9         360.         15/2 +        *               
            10         387.41        9/2 +                        
            11         391.6         7/2 -                        
            12         435.          9/2 -                        
            13         462.         11/2 +                        
            14         469.8         1/2 -                        
            15         488.         11/2 -                        
            16         492.1         3/2 -                        
            17         505.5         5/2 -                        
            18         511.84        7/2 +                        
                                                                  
     Continuum levels were assumed above 538 keV.                 
                                                                  
  mt= 16, 17, 37   (n,2n), (n,3n), and (n,4n)                     
     Calculated with a modified version of gnash /23/.  The       
     neutron transmission coefficients were generated with ecis   
     /19/ and optical model code eliese-3 /24/, respectively,     
     using the above-mentioned deformed and spherical potentials. 
     The level schemes for pu-236, -237, -238, -239 and -240 were 
     taken from refs. /22,25,26,27,28/.  The Gilbert-Cameron's    
     composite formula /29/ was used to represent the level       
     density.  Level density parameters were determined from the  
     observed s-wave resonance spacing /30/ and the level schemes.
     the spin cut-off factors in the constant temperature model   
     were represented by Gruppelaar's prescription /31/.          
                                                                  
                  pu-236    pu-237    pu-238    pu-239    pu-240  
     a   (1/MeV)  25.50      28.00    26.23      29.44    26.96   
     t     (MeV)   0.442      0.416    0.422      0.398    0.412  
     c   (1/MeV)   3.06      14.5      2.88      15.0      3.30   
     E-joint(MeV)  4.71       4.09     4.38       3.97     4.26   
     sigma**2      8.63       8.18     6.47      11.6      9.69   
     no. levels    4.0       19.0     22.0       19.0     28.0    
     E-max (MeV)   0.307      0.4735   1.3103     0.5118   1.2621 
     D-obs  (eV)   0.395     10.7      0.383      9.0      2.3    
     Gamma-g(eV)   0.043      0.027    0.043      0.034    0.043  
                                                                  
     D-obs of pu-236, -237 and -238 were not available from ref.  
     /30/, and hence the parameters "a" for these nuclei were     
     determined assuming its linear dependence on the mass a:     
         a = 0.365*a - 60.64     for even-even pu isotopes        
         a = 0.659*a - 128.18    for odd-mass pu isotopes         
     which were derived by analyzing the data of pu-241, -242,    
     -243, and -244 as well as pu-239 and -240. Low-lying levels  
     were hardly observed for pu-236 and it was assumed to be     
     identical to that of pu-238 to determine the constant        
     temperature parameters.                                      
                                                                  
     Evaluated fission cross section described below was fed to   
     gnash as a competing process/32/.  The preequilibrium process
     was taken into account.  Though the parameter f2 was         
     adjusted, the calculated (n,2n) cross section failed to well 
     reproduce the measured data.  Therefore, the measured (n,2n) 
     cross section of Frehaut et al./33/ was adopted in place of  
     the calculated one.                                          
                                                                  
  mt=18   Fission                                                 
     Below  30 keV                                                
        Based on measurements of ref./34/ and ref./35/.           
     Above  30 keV                                                
        New simultaneous evaluation was performed by              
        Kawano et al./36/                                         
                                                                  
  mt=102  Capture                                                 
     The cross section in the energy range below 1 MeV was derived
     as a product of the evaluated fission cross section and alpha
     value. The alpha values are identical to those of JENDL-2.   
     Above 1 MeV the results of the statistical model calculation 
     with casthy /21/ linked with ecis /19/ were adopted. The     
     photon strength function was normalized in the casthy        
     calculation so as to reproduce the capture cross section of  
     280 mb at 100 keV.                                           
     Direct and semi-direct calculations were performed by Kawano 
     /37/ above 500 keV.                                          
                                                                  
mf=4  Angular distributions of secondary neutrons                 
  mt=2,51-68,91    Calculated with ecis /19/ and casthy /21/.     
  mt=16,17,18,37   Isotropic in the laboratory system.            
                                                                  
mf=5  Energy distributions secondary neutrons                     
  mt=16,17,37,91                                                  
     Calculated with threshold cross section calculation code     
     pegasus /38/ on the basis of preequilibrium and multi-step   
     evaporation model.                                           
     Data for mt=16,17,91 were replaced with gnash calculations   
     performed by Kawano/37/.                                     
  mt=18                                                           
     Distributions were calculated with a modified Madland-Nix    
     model with consideration for multimodal nature of the fission
     process/39,40/.  The compound nucleus formation cross sec-   
     tions for fission fragments were calculated using Becchetti- 
     Greenlees potential/41/.  Up to 3rd-chance-fission were      
     considered at high incident neutron energies.                
     A preequilibrium emission was taken into account above 10 MeV
     as described in Ref./2/. The prefission neutron spectrum     
     was calculated with the Feshbach-Kerman-Koonin theory /42/.  
     The Ignatyuk formula/43/ were used to generate the level     
     density parameters.                                          
        Parameters adopted for thermal-neutron fission/40/:       
           (S1: standard-1, S2: standard-2, S3: standard-3 modes) 
           total average fragment kinetic energy                  
                                           = 190.4 MeV for S1     
                                           = 174.2 MeV for S2     
                                           = 164.2 MeV for S3     
            average energy release         = 205.400 MeV for S1   
                                           = 196.279 MeV for S2   
                                           = 182.123 MeV for S3   
            average mass number of light ff = 105 for S1          
                                            =  99 for S2          
                                            =  83 for s3          
            average mass number of heavy ff = 135 for S1          
                                            = 141 for S2          
                                            = 157 for s3          
            level density of the light ff   = 11.236(S1),         
                                   10.764(S2), 6.669(S3)          
            level density of the heavy ff   = 9.577(S1),          
                                   13.104(S1),16.284(S3)          
            mode branching ratio = 0.248(S1), 0.742(S2), 0.01(S3) 
        These data are essentially based on Schillebeeckx et al.  
        /44/.                                                     
        Note that the parameters vary with the incident energy.   
        Energy-dependent mode branching ratio data of Brosa et al.
        /45/ was used.                                            
  mt=455                                                          
     Taken from Brady and England /46/. Group abundance parameters
     were adjusted so as to reproduce total delayed neutron       
     emission rate measured by Keepin et al./4/, Besant et al.    
     /47/ and Maksyutenko /48/                                    
                                                                  
mf=12  Photon production multiplicities and transition            
       probability arrays                                         
  mt=16,17,37,91,102  (n,2n),(n,3n),(n,4n),inelastic scattering   
                       to the continuum, and capture              
      Data calculated with gnash /23/ were stored under option-1  
      (multiplicities).  The photon branching data were taken from
      refs. /22/ and /25,26,27,28/.  Some assumptions were made   
      for levels of pu-237 and -239 which had no information on   
      branching: if e1 transitions were allowed to lower levels,  
      the transition probabilities were equally shared among them.
      If not, equally shared collective E2 transitions were       
      assumed.  The photon strength functions were represented by 
      the Brink-Axel type giant dipole resonance with conventional
      resonance positions and widths.  They were normalized to    
      input values at the thermal energy.  The pygmy resonance was
      introduced only for pu-240.  The parameters were assumed to 
      be the same as those of u-238 /49/.                         
                                                                  
  mt=18    Fission                                                
      Stored under option-1 (multiplicities).  The thermal neutron
      induced fission gamma spectrum measured by Verbinski /50/   
      was adopted and used up to 20 MeV neutron.  Since no data   
      were given for the photons below 0.14 MeV, it was assumed to
      be the same as that of the photons between 0.14 and 0.3 MeV.
                                                                  
  mt=51-68  Inelastic scattering                                  
      Stored under option-2 (transition probability arrays).  Data
      were taken from ref./22/, and the same assumptions as       
      described above were applied to the levels to which no data 
      were given.                                                 
                                                                  
mf=14  Photon angular distributions                               
    mt=16,17,18,37,51-68,91,102     Isotropic.                    
                                                                  
mf=15  Continuous photon energy spectra                           
    mt=16,17,37,91,102      Calculated with gnash /23/            
    mt=18                   Experimental data by Verbinski /50/   
                            were adopted.                         
                                                                  
mf=31 Covariances of average number of neutrons per fission       
  mt=452                                                          
     Constructed from mt=455 and 456.                             
  mt=455                                                          
     Based on experimental data.  A chi-value was 0.46.           
  mt=456                                                          
     Based on experimental data.  A chi-value was 1.16.           
                                                                  
mf=32 Covariances of resonance paremeters                         
  mt=151                                                          
   Resolved resonance                                             
     The covariances were obtained by using kalman./51/           
   Unresolved resonance                                           
     The covariances were obtained by using kalman./52/           
                                                                  
mf=33 Covariances of cross sections (ref.43)                      
  mt=1                                                            
   Based on experimental data.  A chi-value was 1.29.             
  mt=2                                                            
   Constructed from mt=1, 4, 16, 17, 18, 37, and 102.             
  mt=4, 51-68, 91                                                 
   The covariances were obtained by using kalman /52/.            
   A chi-value was 1.66.                                          
  mt=16                                                           
   Based on experimental data.  A chi-value was 1.0.              
  mt=17                                                           
   Systematics.                                                   
  mt=18                                                           
   Based on simultaneous evaluation /36/.                         
  mt=37                                                           
   Systematics.                                                   
  mt=102                                                          
   Based on experimental data.  A chi-value was 0.47.             
                                                                  
mf=34 Covariances of angular distributions (ref.52)               
  mt=2                                                            
   The covariances of p1 coefficients were obtained by using      
   kalman.  A chi-value was 0.41.                                 
                                                                  
mf=35 Covariances of energy distributions                         
  mt=18                                                           
   The covariances were obtained by using kalman./53/             
                                                                  
                                                                  
References                                                        
 1) Derrien H.: J. Nucl. Sci. Technol., 30, 845 (1993).           
 2) Kawano T. et al.: Phys. Rev., C63, 034601 (2001).             
 3) Tuttle R.J.: INDC(NDS)-107/G + special, 29 (1980).            
 4) Keepin G.R. et al.: Phy. Rev., 107, 1044 (1957).              
 5) Gwin R. et al.: Nucl. Sci. Eng., 94, 365 (1986).              
 6) Frehaut J.: NEANDC(E)-238/L (1986).                           
 7) Gwin R. et al.: Nucl. Sci. Eng., 87, 381 (1984).              
 8) Soleilhac M. et al.: 70 Helsinki , 2, 145 (1970).             
 9) Soleilhac M. et al.: J. Nucl. Energy. 23. 257 (1969).         
10) Nurpeisov B. et al.: At. Energiya, 39, 199 (1975).            
11) Vorodin K.E. et al.: At. Energiya. 33. 901 (1972).            
12) Nakagawa T.: Private communication (2000).                    
13) Uttely C.A.: EANDC(UK)-40 (1964).                             
14) Schwartz R.B. et al.: Nucl. Sci. Eng., 54, 322 (1974).        
15) Foster D.G.Jr. and Glagow D.W.: Phys. Rev., C3, 576 (1971).   
16) Smith A.B. et al.: J. Nucl. Energy, 27, 317 (1973).           
17) Nadolny et al.: C00-3058-39, 33 (1973).                       
18) Poenitz W.P. et al.: Nucl. Sci. Eng., 78, 333 (1981).         
19) Raynal J.: IAEA SMR-9/8 (1970).                               
20) Arthur E.D. et al.: Nucl. Sci. Eng. 88, 56 (1984).            
21) Igarasi S. and Fukahori T.: JAERI 1321 (1991).                
22) Schmorak M.R.: Nucl. Data Sheets, 40, 1 (1983).               
23) Young P.G. et al.: LA-6947 (1977).                            
24) Igarasi S.: JAERI-1224 (1972).                                
25) Schmorak M.R.: Nucl. Data Sheets, 36, 367 (1982).             
26) Ellis-Akovali Y.A.: Nucl. Data Sheets, 49, 181 (1986).        
27) Shurshikov E.N.: Nucl. Data Sheets, 38, 277 (1983).           
28) Shurshikov E.N. et al.: Nucl. Data Sheets, 43, 245 (1984).    
29) Gilbert A. et al.: Can. J. Phys. 43, 1446 (1965).             
30) Mughabghab S.F.: Neutron Cross Sections, Vol 1, Part B (1984).
31) Gruppelaar H.: ECN-13 (1977).                                 
32) Yamamuro N. et al.: JAERI-M 87-025, 347 (1987).               
33) Frehaut J. et al.: CEA-N-2500 (1986).                         
34) Gayther D.B.: 1975 Washington, 2, 560 (1975).                 
35) Wagemans C. et al.: Ann. Nucl. energy, 7, 495 (1980).         
36) Kawano T. et al.: JAERI-Research 2000-004 (2000).             
37) Kawano T.: Private communication (1999).                      
38) Iijima S. et al.: JAERI-M 87-025, p.337 (1987).               
39) Madland D.G. and Nix J.R.: Nucl. Sci. Eng., 81, 213 (1982).   
40) Ohsawa, T. et al.: Nucl. Phys. A665, 3 (2000).                
41) Becchetti Jr.F.D. and Greenlees G.W.: Phys. Rev., 182, 1190   
    (1969).                                                       
42) Feshbach H., et al.: Ann. Phys. (N.Y.) 125, 429 (1980).       
43) Ignatyuk A.V.: Sov. J. Nucl. Phys., 29, 450 (1979).           
44) Schillebeeckx P. et al.: Nucl. Phys. A545, 623 (1992).        
45) Brosa U. et al.: Phys. Rev. C59, 767 (1999).                  
46) Brady M.C. and England T.R.: Nucl. Sci. Eng., 103, 129 (1989).
47) Besant C.B. et al.: J. Br. Nucl. Energy Soc., 16, 161         
    (1977)                                                        
48) Maksyutenko B.P.: Yad. Fiz. (English Translation) 15,         
    848 (1963)                                                    
49) Hida K.: JAERI-M 85-035, 166 (1985).                          
50) Verbinski V.V. et al.: Phys. Rev., C7, 1173 (1973).           
51) Kawano T.: Private communication (2000).                      
52) Shibata K. et al.: JAERI-Research 97-074 (1997).              
53) Kawano T. et al.: JAERI-Research 99-009 (1999).               
                                                                  
================================================================= 
APPENDIX          RESONANCE DATA                                  
================================================================= 
                                                                  
     THE PRESENT FILE CONTAINS THE RESONANCE PARAMETERS OBTAINED  
FROM A SAMMY FIT ANALYSIS OF HIGH RESOLUTION EXPERIMENTAL DATA,   
PERFORMED AT ORNL(OAK RIDGE NATIONNAL LABORATORY,USA) BY H.DERRIEN
AND G.DE SAUSSURE AND AT JAERI(TOKAI-MURA RESEARCH ESTABLISHMENT, 
JAPAN) BY H.DERRIEN.                                              
   THE FILE CONTAINS THREE INDEPENDANT SECTIONS:                  
   1/ THE FIRST CORRESPONDS TO THE ENERGY RANGE 0 KEV TO 1 KEV.   
THE CORRESPONDING SET OF RESONANCE PARAMETRES CONTAINS 398 RESO-  
NANCES IN THE ENERGY RANGE 0 KEV TO 1 KEV, 4 FICTICIOUS NEGATIVE  
ENERGY RESONANCES AND 3 FICTICIOUS RESONANCES ABOVE 1 KEV;        
   2/ THE SECOND CORRESPONDS TO THE ENERGY RANGE 1 KEV TO 2 KEV.  
THE CORRESPONDING SET OF RESONANCE PARAMETERS CONTAINS 435 RESON- 
ANCES IN THE ENERGY RANGE 0.980 KEV TO 2.02 KEV, 3 FICTICIOUS     
RESONANCES BELOW 0.9 KEV AND 3 FICTICIOUS RESONANCES ABOVE 2.02   
KEV;                                                              
   3/ THE THIRD CORRESPONDS TO THE ENERGY RANGE 2 KEV TO 2.5 KEV. 
THE CORRESPONDING SET OF RESONANCE PARAMETERS CONTAINS 218 RESO-  
NANCES IN THE ENERGY RANGE 1.98 KEV TO 2.53 KEV, 3 FICTICIOUS     
RESONANCES BELOW 1.98 KEV AND 3 FICTICIOUS RESONANCES ABOVE 2.53  
KEV.                                                              
   IN ALL SECTIONS THE FICTICIOUS RESONANCE PARAMETERS TAKE INTO  
ACCOUNT THE CONTRIBUTION OF ALL THE EXTERNAL TRUNCATED RESONANCES 
IN SUCH A WAY THAT NO TOTAL, SCATTERING, FISSION AND CAPTURE      
SMOOTH FILES ARE NEEDED IN THE CORRESPONDING ENERGY RANGES FOR THE
REPRODUCTION OF THE CROSS SECTIONS WITHIN THE EXPERIMENTAL ERRORS.
   THE FOLLOWING EXPERIMENTAL DATA BASE HAS BEEN USED IN THE SAMMY
FITS:                                                             
  -ABSORPTION AND FISSION FROM R.GWIN ET AL./1,2/;                
  -FISSION FROM R.GWIN ET AL./3,4/, J.BLONS/5/, L.W.WESTON ET     
   AL./6,7/;                                                      
  -TRANSMISSION FROM R.R.SPENCER ET AL./8/, J.A.HARVEY ET AL./9/  
PRIOR TO THE FITS THE EXPERIMENTAL FISSION AND ABSORPTION CROSS   
SECTIONS WERE NORMALISED, DIRECTLY OR INDIRECTLY TO THE 0.0253 EV 
VALUES OBTAINED BY THE ENDF/B-VI STANDARD EVALUATION GROUP/10/.   
THE TRANSMISSION DATA WERE CONSIDERED AS ACCURATE ABSOLUTE MEASU- 
REMENTS(R.R.SPENCER TOTAL CROSS SECTION AT 0.0253 EV IS 1025.0 B  
IN EXCELLENT AGREEMENT WITH THE 1027.3 B STANDARD VALUE).         
   DETAILS ON THE ANALYSIS ARE FOUND IN REFERENCES/11,12,13/      
                                                                  
***************************************************************** 
         COMMENTS ON THE THERMAL AND LOW ENERGY RANGES            
***************************************************************** 
                                                                  
     THE THERMAL CROSS SECTION VALUES CALCULATED AT 293 K BY THE  
RESONANCE PARAMETERS OF THE FIRST SECTION ARE GIVEN IN THE FOLLO- 
WING TABLE:                                                       
                                                                  
                                                                  
              SAMMY      RESENDD              PROPOSED            
                  293 K (BARN)        STANDARD VALUES(BARN)/10/   
****************************************************************  
FISSION       747.64     747.90           747.99+-1.87            
CAPTURE       271.10     270.73           271.43+-2.14            
SCATTERING      7.97       7.99             7.88+-0.97            
TOTAL        1026.71    1026.62          1027.30+-5.00            
****************************************************************  
                                                                  
     ONE SHOULD NOTE THAT THE 293 K CROSS SECTIONS CALCULATED AT  
0.0253 EV DEPEND ON THE WAY THE DOPPLER BROADENING CALCULATION IS 
PERFORMED. FOR INSTANCE USING A GAUSSIAN BROADENING FUNCTION WILL 
GIVE A FISSION CROSS SECTION ABOUT 2.5 BARNS LARGER THAN THE ONE  
OBTAINED FROM THE ACCURATE CALCULATION WHICH CONSERVES THE 1/V    
SHAPE OF THE THERMAL CROSS SECTION. THE VALUES GIVEN IN THE TABLE 
ABOVE WERE OBTAINED FROM SAMMY (LEAL-HWANG METHOD)/14,15/ AND FROM
RESENDD WITH 0.1% FOR THE INTERPOLATION ACCURACY/16/.             
    THE FOLLOWING TABLE SHOWS EXPERIMENTAL CROSS SECTIONS AVE-    
RAGED OVER THE ENERGY RANGES 0.02 EV TO 0.06 EV AND 0.02 EV TO    
0.65 EV, COMPARED TO THE CALCULATED VALUES:                       
                                                                  
                                                                  
                  AVERAGE CROSS-SECTIONS(BARN)                    
****************************************************************  
 REFERENCES(1-10)   0.02 TO 0.06 EV        0.02 TO 0.65 EV        
****************************************************************  
                   EXP     CALC (293K)     EXP    CALC (293K)     
GWIN71 FISS       631.41                  843.71                  
GWIN76 FISS       631.41                  838.39                  
GWIN84 FISS(*)    631.41  631.75(+0.05%)  837.18  838.69(+0.18%)  
DERUYTER70 FISS   631.41                  859.43                  
WAGEMANS80 FISS   631.41                  862.56                  
WAGEMANS88 FISS   631.41                  841.80                  
GWIN71 CAPTURE    243.84  243.22(-0.25%)  524.75  518.13(-1.26%)  
GWIN76 ABSORPT(*) 875.90  874.29(-0.18%) 1359.96 1357.14(-0.21%)  
SPENCER84 TOT(*)  883.20  882.86(-0.04%) 1361.69 1367.6 (+0.43%)  
****************************************************************  
(*)THESE DATA HAD THE LARGIEST WEIGHT IN THE THERMAL FIT. THE VA- 
LUES BETWEEN THE PARENTHESES GIVE THE PERCENTAGE DEVIATION BETWEEN
THE CALCULATED DATA AND THE EXPERIMENTAL DATA.                    
***************************************************************** 
                                                                  
     THE VALUE OF 631.4 BARNS FOR ALL THE AVERAGED EXPERIMENTAL   
FISSION CROSS SECTIONS IN THE ENERGY RANGE 0.02 EV TO 0.06 EV     
CORRESPONDS TO THE RENORMALISATION OF THE FISSION EXPERIMENTS TO  
748.0+-1. BARNS AT 0.0253 EV. ORNL DATA ARE CONSISTENT WITHIN 0.8%
OVER THE ENERGY RANGE 0.02 EV TO 0.65 EV (I.E. OVER THE 0.3 EV    
RESONANCE). DERUYTER 1970 AND WAGEMANS 1980 DATA ARE ABOUT 2.5%   
LARGER AND WERE NOT INCLUDED IN THE SAMMY FIT. WHEN NORMALIZED ON 
THE STANDARD VALUE AT 0.0253 EV, GWIN 76 ABSORPTION AGREES WITH   
THE ABSORPTION OBTAINED FROM SPENCER TOTAL CROSS SECTION WITHIN   
0.7% OVER THE 0.3 EV RESONANCE. THE PRESENT EVALUATION IS         
ESSENTIALLY THE RESULT OF A CONSISTENT SAMMY ANALYSIS OF ALL THE  
AVAILABLE ORNL DATA WITH A LARGER WEIGHT ON GWIN 1984 FISSION,    
GWIN 1976 ABSORPTION AND SPENCER TRANSMISSION DATA.               
     AFTER RENORMALIZATION OF THE CALCULATED FISSION CROSS SECTION
ON THE PRELIMINARY 1991 WESTON AND TODD FISSION DATA(SEE NEXT     
SECTION) A SLIGHT ADJUSTMENT OF THE NEGATIVE RESONANCE PARAMETERS 
WAS PERFORMED TO KEEP THE VALUES CALCULATED AT 0.0253 EV IN CLOSE 
AGREEMENT WITH THE STANDARD VALUES. THE 1988 DATA OF WAGEMANS ET  
AL./17/ AGREE WITHIN 0.4% WITH THE CALCULATED VALUES OVER THE     
ENERGY RANGE FROM 0.02 EV TO 0.65 EV AFTER ADJUSTMENT OF THE      
ENERGY SCALE TO THE ORNL SCALE (THE DIFFERENCE WAS 0.27 EV AT 20  
EV BETWEEN 1988 WAGEMANS AND ORNL SAMMY FIT ENERGY SCALES).       
                                                                  
***************************************************************** 
         COMMENTS ON THE 0 KEV TO 1 KEV ENERGY RANGE.             
***************************************************************** 
                                                                  
   AT THE END OF 1987, AN ANALYSIS WAS COMPLETED UP TO 1 KEV. IN A
PRELIMINARY STEP, A CORRELATED FIT OF HARVEY TRANSMISSION DATA,   
WESTON 84 FISSION DATA AND BLONS FISSION DATA WAS PERFORMED, WITH 
POSSIBLE ADJUSTMENT OF THE NORMALIZATION COEFFICIENTS AND OF THE  
BACKGROUND CORRECTIONS. THIS PRELIMINARY STEP HAS SHOWN THAT THIS 
ADJUSTMENT WAS NOT NECESSARY TO HAVE CONSISTENCY BETWEEN HARVEY   
DATA AND WESTON DATA. BLONS DATA NEEDED A LARGE READJUSTMENT OF   
THE BACKGROUND AND OF THE NORMALIZATION. THEREFORE, THE FINAL FIT 
WAS PERFORMED ONLY ON HARVEY TRANSMISSION DATA, GWIN 84 FISSION   
DATA (BELOW 30 EV) AND WESTON 84 FISSION DATA, WITH NO BACKGROUND 
AND NORMALISATION ADJUSTMENT. BLONS DATA, WHICH HAVE BETTER       
RESOLUTION THAN WESTON 84 DATA, WERE USED ONLY TO OBTAIN MORE     
ACCURATE FISSION WIDTHS OF SOME NARROW RESONANCES IN THE HIGH     
ENERGY RANGE.                                                     
   IN 1989, PRELIMINARY RESULTS OF THE 1988 WESTON FISSION        
MEASUREMENT/7/ WERE INCLUDED IN THE SAMMY EXPERIMENTAL DATA       
BASE.  ONE EXPECTED FROM THIS MEASUREMENT, WHICH WAS PERFORMED BY 
USING A 86 M FLIGHT PATH WITH A RESOLUTION COMPARABLE TO THE      
RESOLUTION OF HARVEY TRANSMISSION, A CONFIRMATION OF THE EXCELLENT
QUALITY OF THE 1984 MEASUREMENT. A CONSISTENT SAMMY FIT OF HARVEY 
TRANSMISSION, WESTON 84 FISSION AND PRELIMINARY WESTON 88 FISSION 
WAS RESTARTED FROM THE PARAMETER AND COVARIANCE FILES OBTAINED IN 
1987.  IT APPEARED THAT LARGE BACKGROUND AND NORMALISATION        
CORRECTIONS WERE NEEDED ON THE NEW WESTON FISSION TO OBTAIN       
CONSISTENCY WITH HARVEY TRANSMISSION DATA. THESE CORRECTIONS WERE 
COMPARABLE TO THOSE FOUND ON BLONS DATA AND WERE NOT UNDERSTOOD BY
THE AUTHORS OF THE EXPERIMENT. THE LAST SAMMY RUNS WERE PERFORMED 
BY NOT ALLOWING BACKGROUND AND NORMALIZATION VARIATIONS ON HARVEY 
TRANSMISSION AND WESTON 84 FISSION(VERY SMALL ERROR BARS WERE     
ASSIGNED TO THE CORRESPONDING PARAMETERS IN THE COVARIANCE MATRIX)
AND BY ALLOWING THESE VARIATIONS ON WESTON 88 DATA. A NEW SET OF  
RESONANCE PARAMETERS WAS OBTAINED,WHICH WAS IMPROVED COMPARED TO  
THE PREVIOUS SET DUE TO THE VERY HIGH RESOLUTION OF THE NEW WESTON
FISSION MEASUREMENT.                                              
   THE CALCULATED AVERAGE FISSION CROSS SECTION IN THE ENERGY     
RANGE FROM 0.1 KEV TO 1.0 KEV WAS 3.7% SMALLER THAN THE VALUES    
OBTAINED BY THE ENDF/B-VI STANDARD EVALUATION GROUP, DUE TO THE   
FACT THAT WESTON 84 DATA WERE 3.1% LOWER THAN THE AVERAGE STANDARD
VALUE. A NEW MEASUREMENT WAS PERFORMED BY WESTON AND TODD IN 1991 
/18/ IN ORDER TO CHECK THEIR 1984 DATA. A CAREFUL NORMALIZATION   
OF THE DATA IN THE THERMAL ENERGY RANGE SHOWED THAT THE 1984 DATA 
SHOULD BE RENORMALIZED BY ABOUT +3%. TO TAKE INTO ACCOUNT THIS    
RENORMALIZATION, THE 1989 RESONANCE PARAMETERS WERE MODIFIED AT   
JAERI/13/ IN THE FOLLOWING WAY:                                   
   1/ INCREASE OF THE FISSION WIDTH BY 3% AND DECREASE OF THE     
CAPTURE WIDTH BY A QUANTITY EQUAL TO THE VARIATION OF THE FISSION 
WIDTH, IN THE NARROW RESONANCES(MAINLY 1+ RESONANCES); THAT DOES  
NOT MODIFY THE TOTAL CROSS SECTION IN THE CORRESPONDING           
RESONANCES;                                                       
   2/ ADJUSTMENT OF THE NEUTRON WIDTH OF THE 0+ RESONANCES BY A   
REFIT OF THE TRANSMISSION DATA AND OF THE RENORMALIZED WESTON AND 
TODD 1984 DATA IN ENERGY RANGES WHERE THE CONTRIBUTION OF THE 0+  
RESONANCES IS DOMINANT, AND INCREASE OF THE OTHER(SMALL) 0+       
NEUTRON WIDTHS BY 3%. NO SEVERE INCONSISTENCY WAS OBSERVED BETWEEN
THE TRANSMISSION DATA AND THE NEW FISSION DATA OVER THE DOMINANT  
0+ RESONANCES;THE DIFFERENCES BETWEEN THE 1989 FITS OF THE TRANS- 
MISSION AND THE NEW FITS WERE CONSISTENT WITHIN THE EXPERIMENTAL  
ERROR BARS.                                                       
   THE FOLLOWING TABLE SHOWS THE FISSION CROSS SECTIONS CALCULA-  
TED FROM THE RESONANCE PARAMETERS, THE EXPERIMENTAL VALUES AND THE
RESULTS OF THE ENDF/B-VI STANDARD EVALUATION GROUP AVERAGED IN THE
SAME ENERGY INTERVALS. WESTON 1991 DATA ARE PRELIMINARY. WESTON   
1984 DATA ARE NORMALIZED ON PRELIMINARY WESTON 1991:              
                                                                  
                           CROSS-SECTIONS(BARN)                   
         *************************************************        
            ENERGY    CALCUL   WESTON   WESTON   STANDARD         
             (EV)               1991     1984                     
         *************************************************        
          0.010-10.    80.12    79.98                             
              9-20     94.74    94.91                             
             20-40     17.52    17.76    17.97                    
             40-60     50.64    50.90    50.87                    
             60-100    54.42    54.38    54.33                    
            100-200    18.63    18.59    18.56    18.66           
            200-300    17.85             17.89    17.88           
            300-400     8.31              8.34     8.43           
            400-500     9.59              9.58     9.57           
         -------------------------------------------------        
            200-500    11.92    11.93    11.93    11.96           
         -------------------------------------------------        
            500-600    15.39             15.57    15.86           
            600-700     4.37              4.30     4.46           
            700-800     5.51              5.53     5.63           
            800-900     4.84              4.89     4.98           
            900-1000    8.33              8.38     8.30           
         -------------------------------------------------        
            500-1000    7.69     7.73     7.73     7.79           
         -------------------------------------------------        
             20-1000   13.09    13.11    13.11                    
         **************************************************       
                                                                  
                                                                  
   GWIN 1971 AND 1976 ABSORPTION DATA WERE NOT INCLUDED IN THE    
SAMMY FIT IN THE ENERGY RANGE ABOVE 1 EV. ACCURATE ABSORPTION     
CROSS SECTIONS SHOULD BE CALCULATED FROM THE PARAMETERS OBTAINED  
FROM THE ANALYSIS OF THE TRANSMISSION AND FISSION DATA. THE FOLLO-
WING TABLE SHOWS THE CALCULATED AVERAGE VALUES OF THE CAPTURE, AB-
SORPTION AND ALPHA COMPARED TO GWIN 1971 AND GWIN 1976 DATA. THE  
CALCULATIONS WERE PERFORMED WITH RESENDD, 1.0 % ACCURACY:         
                                                                  
                     CROSS-SECTIONS(BARN)                         
    *******************************************************       
      ENERGY(EV)   CALC. VALUES (293K)     GWIN DATA              
    *******************************************************       
                  CAPT   ABSORP ALPHA     ABSORP ALPHA            
       7.3- 16.0  76.61  196.04  0.64     208.00  0.74(*)         
      16.0- 37.5  20.51   44.55  0.85      46.50  0.89(*)         
      37.5- 50.0  48.72   70.00  2.29      83.15  2.96(*)         
      50.0-100.0  33.60   92.13  0.57      92.84  0.63            
     100.0-200.0  15.58   34.29  0.83      33.66  0.87            
     200.0-300.0  15.85   33.68  0.89      34.69  0.94            
     300.0-400.0   9.69   18.01  1.16      18.31  1.16            
     400.0-500.0   3.96   13.56  0.41      13.56  0.44            
     500.0-600.0  10.87   26.30  0.70      26.54  0.72            
     600.0-700.0   6.53   10.90  1.49      11.57  1.54            
     700.0-800.0   4.95   10.47  0.90      10.52  0.97            
     800.0-900.0   3.65    8.50  0.75       9.30  0.82            
     900.0-999.9   5.06   13.51  0.60      13.23  0.70            
    ******************************************************        
     (*) GWIN 1971 DATA                                           
                                                                  
   IF ONE EXCEPTS THE ENERGY RANGE 37.5-50 EV, THE CALCULATED AB- 
SORPTION VALUES AGREE WELL WITH GWIN EXPERIMENTAL DATA; THEY ARE  
ON AVERAGE 1.2% LOWER IN THE ENERGY RANGE FROM 50 EV TO 1000 EV.  
                                                                  
***************************************************************** 
      COMMENTS ON THE 1 KEV TO 2 KEV ENERGY RANGE                 
***************************************************************** 
                                                                  
   PRELIMINARY RESONANCE PARAMETERS WERE OBTAINED IN 1989 FROM THE
ANALYSIS OF THE HARVEY THICK SAMPLE TRANSMISSION DATA AND OF THE  
PRELIMINARY RESULTS OF WESTON 88 FISSION MEASUREMENT.  DUE TO LACK
OF TIME, THE MEDIUM AND THIN SAMPLE TRANSMISSION DATA WERE NOT    
INCLUDED IN THE SAMMY DATA BASE, AND THE CONTRIBUTION OF THE      
TRUNCATED EXTERNAL RESONANCES WAS NOT CAREFULLY INVESTIGATED.     
NEVERTHELESS, THE RESULTS WERE USED IN THE ENDF/B-VI FILE, ALONG  
WITH A SMOOTH FILE IN ORDER TO AGREE WITH THE AVERAGE VALUES OF A 
PREVIOUS ENDF/B-VI EVALUATION (THIS PRELIMINARY SET OF PARAMETERS 
WAS CONSIDERED AS MORE USEFUL THAN THE STATISTICAL PARAMETERS IN  
THE ENERGY RANGE 1 KEV TO 2 KEV FOR THE CALCULATION OF THE SELF-  
SHIELDING FACTORS).                                               
   THE ANALYSIS WAS RESTARTED IN APRIL 1991 AT JAERI(TOKAI        
RESEARCH ESTABLISHMENT) WITH AN UPDATED VERSION OF SAMMY ADAPTED  
BY T.NAKAGAWA TO THE FACOM 780. THE PRELIMINARY SET OF PARAMETERS 
OBTAINED AT OAK RIDGE IN 1989 WAS USED AS PRIOR INFORMATIONS TO   
START THE SAMMY CALCULATIONS. ALSO PRIOR TO THE ANALYSIS, THE CON-
TRIBUTION OF THE EXTERNAL RESONANCES WAS CALCULATED BY USING THE  
SET OF THE 0 KEV TO 1 KEV KNOWN RESONANCES, SHIFTED IN THE ENERGY 
RANGES -1 KEV TO 0 KEV, 2 KEV TO 3KEV AND 3 KEV TO 4 KEV; EQUIVA- 
LENT CONTRIBUTION WAS OBTAINED BY USING 3 FICTICIOUS RESONANCES   
BELOW 1 KEV AND 3 FICTICIOUS RESONANCES ABOVE 2 KEV(SEE DETAILS IN
REF./13/). THE ANALYSIS WAS PERFORMED ON THE THICK AND MEDIUM     
SAMPLE TRANSMISSIONS OF HARVEY DATA (THE THIN SAMPLE DATA WAS NOT 
USEFUL IN THE HIGH ENERGY RANGE) AND ON THE 1988 FISSION DATA RE- 
LEASED BY WESTON AT THE BEGINNING OF 1991/7/. THE DEFINITIVE      
SAMMY FITS WERE PERFORMED IN APRIL 1992 AFTER RENORMALIZATION OF  
THE 1988 DATA OF WESTON ON THE ENDF/B-VI STANDARD VALUES BETWEEN 1
KEV AND 2 KEV, IN AGREEMENT WITH THE 1991 NEW MEASUREMENTS OF     
WESTON AND TODD.                                                  
   THE AVERAGE CROSS SECTIONS CALCULATED FROM THE RESONANCE       
PARAMETERS ARE COMPARED TO THE EXPERIMENTAL VALUES IN THE FOLLO-  
WING TABLE:                                                       
                                                                  
                                                                  
**************************************************************    
                        CROSS-SECTIONS(BARN)                      
           ---------------------------------------------------    
                 TOTAL           FISSION         CAPTURE          
  ENERGY    --------------    -------------    -------------      
   KEV     CALC(A)   EXP(B)  CALC(A)   EXP(C) CALC(A)  EXP(D)     
**************************************************************    
  1.0-1.1   24.47    24.95    5.549    5.581   4.728   5.04       
  1.1-1.2   22.82    23.10    5.985    6.017   3.757   2.95       
  1.2-1.3   22.29    22.90    4.601    4.501   4.287   4.00       
  1.3-1.4   22.63    22.85    6.997    6.997   3.012   2.52       
  1.4-1.5   20.42    20.95    4.041    4.059   3.450   3.57       
  1.5-1.6   18.30    18.95    2.564    2.613   3.521   3.89       
  1.6-1.7   21.82    21.90    3.952    3.955   3.833   4.36       
  1.7-1.8   21.26    21.35    3.400    3.425   4.091   4.37       
  1.8-1.9   23.76    23.30    5.178    5.187   3.639   3.14       
  1.9-2.0   18.48    18.90    2.152    2.180   3.205   4.06       
**************************************************************    
  1.0-2.0   21.63    21.92    4.442    4.446   3.752   3.79       
**************************************************************    
 (A) TOTAL, FISSION AND CAPTURE CROSS SECTIONS CALCULATED BY      
     RESENDD FROM THE RESONANCE PARAMETERS.                       
 (B) EXPERIMENTAL TOTAL CROSS SECTIONS FROM REFERENCE/19/.        
 (C) WESTON AND TODD 1988 HIGH RESOLUTION FISSION CROSS SECTIONS  
     FROM REFERENCE/7/ NORMALIZED TO ENDF/B-VI STANDARD IN THE    
     ENERGY RANGE FROM 1.0 KEV TO 2.0 KEV.                        
 (D) GWIN 1971 EXPERIMENTAL DATA NORMALIZED TO GWIN 1976 DATA.    
**************************************************************    
                                                                  
   THE DIFFERENCE OF 1.3% BETWEEN THE AVERAGE CALCULATED TOTAL    
CROSS SECTION AND THE AVERAGE EXPERIMENTAL CROSS SECTION IN THE   
ENERGY RANGE FROM 1.0 KEV AND 2.0 KEV IS MAINLY DUE TO THE METHOD 
OF EVALUATING THE TOTAL CROSS SECTION FROM THE EFFECTIVE CROSS    
SECTION IN REFERENCE/19/. THE ACCURACY OF THE SAMMY FIT OF THE    
EXPERIMENTAL TRANSMISSION DATA IS BETTER THAN 0.5% ON THE CROSS   
SECTION. THE CALCULATED FISSION CROSS SECTIONS ARE IN VERY GOOD   
AGREEMENT WITH THE EXPERIMENTAL DATA. THE CAPTURE DATA /1/ ARE    
AVERAGE VALUES OBTAINED FROM THE DATA AVAILABLE IN THE EXFOR FILE 
AND NORMALIZED TO GWIN 1976 AVERAGE VALUES; THERE ARE LARGE       
DIFFERENCES BETWEEN THE CALCULATED DATA AND THE EXPERIMENTAL DATA 
AVERAGED OVER 0.1 KEV INTERVALS; BUT ON THE INTERVAL FROM 1.0 KEV 
TO 2.0 KEV THE AVERAGE VALUES ARE CONSISTENT WITHIN 1.0%.         
                                                                  
***************************************************************** 
   COMMENTS ON THE 2.0 KEV TO 2.5 KEV REGION                      
***************************************************************** 
                                                                  
   THIS ENERGY RANGE WAS ALSO ANALYSED AT JAERI /13/. NO          
PRELIMINARY SET OF RESONANCE PARAMETERS WAS AVAILABLE PRIOR TO THE
ANALYSIS. MORE THAN 90% OF THE RESONANCES, COMPARED TO THE LOW    
ENERGY RANGE, COULD STILL BE IDENTIFIED IN THE TRANSMISSION DATA  
BETWEEN 2 KEV AND 2.5 KEV. THEREFORE THE CORRELATED SAMMY ANALYSIS
OF HARVEY TRANSMISSIONS AND WESTON FISSION WAS STILL FEASIBLE IN  
THIS ENERGY RANGE. THE RESONANCE PARAMETERS OBTAINED ARE          
CONSISTENT AND HAS NEARLY THE SAME STATISTICAL PROPERTIES AS THOSE
OF THE RESONANCES IN THE 0 TO 2 KEV ENERGY RANGE. A QUITE GOOD FIT
OF THE TRANSMISSION AND FISSION DATA WAS OBTAINED WITHOUT         
BACKGROUND AND NORMALISATION ADJUSTMENT. HOWEVER, THE CALCULATED  
FISSION CROSS SECTIONS ARE, ON AVERAGE, 1.4% LOWER THAN THE       
EXPERIMENTAL VALUES.  THIS DIFFERENCE,WHICH HOWEVER IS NOT LARGER 
THAN THE SYSTEMATIC ERRORS ON THE EXPERIMENTAL DATA, COULD BE DUE 
TO THE DIFFICULTIES OF IDENTIFYING THE WIDE J=0+ RESONANCES IN THE
EXPERIMENTAL DATA, BECAUSE THE EFFECTS OF THE INCREASING          
RESOLUTION AND DOPPLER WIDTHS. PRIOR TO THE SAMMY FITS, THE       
FISSION DATA OF WESTON AND TODD (1988 HIGH RESOLUTION DATA) WERE  
NORMALIZED TO THE ENDF/B-VI STANDARD IN THE ENERGY RANGE FROM 1   
KEV TO 2 KEV.                                                     
   THE CROSS SECTIONS,CALCULATED FROM THE RESONANCE PARAMETERS    
AND AVERAGED OVER 0.1 KEV INTERVALS,ARE GIVEN IN THE FOLLOWING    
TABLE:                                                            
                                                                  
**************************************************************    
                         CR0SS-SECTIONS(BARN)                     
                ------------------------------------------        
                    TOTAL            FISSION       CAPTURE        
      ENERGY    --------------    --------------   -------        
       (KEV)   CALC(A)   EXP(B)  CALC(A)   EXP(C)  CALC(A)        
**************************************************************    
      2.0-2.1   17.34    17.30    2.034    2.062    3.223         
      2.1-2.2   20.27    19.80    2.949    2.999    4.051         
      2.2-2.3   19.34    19.10    2.357    2.393    3.324         
      2.3-2.4   21.28    21.20    3.646    3.679    3.640         
      2.4-2.5   20.03    20.60    3.956    4.024    3.128         
**************************************************************    
      2.0-2.5   19.65    19.60    2.989    3.031    3.473         
**************************************************************    
  (A) TOTAL, FISSION AND CAPTURE CROSS SECTIONS CALCULATED BY     
      RESENDD, 1% ACCURACY, AT 300 K,FROM THE RESONANCE PARAME-   
      TERS.                                                       
  (B) AVERAGE TOTAL CROSS SECTIONS OBTAINED FROM THE AVERAGE      
      EXPERIMENTAL EFFECTIVE CROSS SECTIONS IN REFERENCE/19/.     
  (C) 1988 HIGH RESOLUTION DATA OF WESTON AND TODD NORMALIZED     
      TO ENDF/B-VI STANDARD IN THE ENERGY RANGE FROM 1 KEV TO     
      2 KEV.                                                      
***************************************************************** 
                                                                  
                                                                  
***************************************************************** 
      FISSION AND CAPTURE RESONANCE INTEGRALS                     
***************************************************************** 
                                                                  
THE FISSION AND CAPTURE RESONANCE INTEGRALS ARE COMPARED TO       
JENDL-3 DATA IN THE FOLLOWING TABLE:                              
                                                                  
   **********************************************************     
     ENERGY RANGE(EV)    FISSION(BARN)      CAPTURE(BARN)         
   **********************************************************     
                        JENDL-3  PRESENT    JENDL-3  PRESENT      
       0.5 -   5.0       85.725   84.879     28.651   28.723      
       5.0 -  10.0       25.081   25.147     19.059   18.950      
      10.0 -  50.0       96.856   99.715     77.181   74.686      
      50.0 - 100.0       40.479   41.552     25.930   25.376      
     100.0 - 301.0       19.677   20.252     17.952   17.729      
     301.0 -1000.0       10.047   10.317      8.348    8.418      
    1000.0 -2000.0        3.484    3.206      2.840    2.634      
    2000.0 -2.E+07       17.783  (17.783)     5.224   (5.224)     
   **********************************************************     
         TOTAL          299.132  302.851    185.185  181.739      
   **********************************************************     
                                                                  
   THE JENDL-3 RESONANCE PARAMETERS ARE THOSE OBTAINED IN 1987 IN 
THE ENERGY RANGE 0 KEV TO 1 KEV. THEY ARE SLIGTHLY DIFFERENT FROM 
THOSE PUBLISHED IN 1989. THAT EXPLAINS THE SMALL DIFFERENCES OB-  
SERVED BETWEEN JENDL-3 AND THE PRESENT RESULTS IN THIS ENERGY RAN-
GE. IN THE ENERGY RANGE 1 KEV TO 2 KEV JENDL-3 IS UNRESOLVED      
RANGE.  THE FISSION AND CAPTURE RESONANCE INTEGRALS CALCULATED    
FROM ENDF/B-V AND THOSE FOUND IN BNL-325 ARE THE FOLLOWING:       
                                                                  
      ENDF/B-V     FISSION: 302.13 B    CAPTURE: 194.10 B         
       BNL-325     FISSION: 310+-10 B   CAPTURE: 200+-20 B        
                                                                  
   THE CONSEQUENCE OF CHANGING FROM THE OLD SETS OF RESONANCE     
PARAMETERS(ENDF/B-V AND PREVIOUS SETS) TO THE NEW SET IS THAT     
THE CAPTURE RESONANCE INTEGRAL WILL DECREASE BY 6.7% COMPARED     
WITH ENDF/B-V VALUE.                                              
                                                                  
REFERENCES OF APPENDIX                                            
 1) R.GWIN ET AL.,NUCL.SCI.ENG.,45,25(1971)                       
 2) R.GWIN ET AL.,NUCL.SCI.ENG.,59,79(1976)                       
 3) R.GWIN ET AL.,NUCL.SCI.ENG.,61,116(1976)                      
 4) R.GWIN ET AL.,NUCL.SCI.ENG.,88,37(1984)                       
 5) J.BLONS, NUCL.SCI.ENG.,51,130(1973)                           
 6) L.W.WESTON ET AL.,NUCL.SCI.ENG.88,567(1984)                   
 7) L.W.WESTON ET AL.,TO BE PUBLISHED(HIGH RESOLUTION 1988 DATA)  
 8) R.R.SPENCER ET AL.,NUCL.SCI.ENG.,96,318(1987)                 
 9) J.A.HARVEY ,MITO 1988,PAGE 115                                
10) A.CARLSON ET AL.,PRELIMINARY RESULTS OF THE ENDF/B-6 STANDARD 
   EVALUATION(SEPT 8 1987)                                        
11) H.DERRIEN AND G. DE SAUSSURE,ORNL-TM-10986(1988)              
12) H.DERRIEN ET AL.,NUCL.SCI.ENG.,106,434(1990)                  
13) H.DERRIEN, J.NUCL>SCI.TECHNOL.,30,845(1993).                  
14) N.M.LARSON ET AL.,ORNL/TM-7485,ORNL/TM-9179,ORNL/TM-9719/R1   
15) L.LEAL AND R.N.HWANG,TRANS.AM.NUC.SOC.,55,340(1987)           
16) T.NAKAGAWA,RESENDD A JAERI VERSION OF RESEND,JAER=-M 84-192   
    (1984).                                                       
17) C.WAGEMANS ET AL.,MITO 1988,PAGE 91                           
18) L.W.WESTON,PRIVATE COMMUNICATION(1992)                        
19) H.DERRIEN,J.NUCL.SCI.TECHNOL.,29,794(1992).