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  8-O - 17 NEA        RCOM-JUN91 JEF SCG                          
                      DIST-JAN09                     20090105     
----JEFF-311          MATERIAL  828                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
***************************  JEFF-3.1.1  *************************
**                                                              **
**         Original data taken from:  JEFF-3.1                  **
**                                                              **
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*****************************  JEFF-3.1  *************************
**                                                              **
**         Original data taken from:  JEFF-3.0                  **
**                                                              **
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*****************************  JEFF-3.0  *************************
                                                                  
   DATA TAKEN FROM   :-   JEF-2.2 (DIST-JAN92)                    
                                                                  
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*   JEF-2                                                        *
*     DATA WERE TAKEN FROM ENDF/B-VI EVALUATION.                 *
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  8-O - 17 BNL        EVAL-JAN78 B.A.MAGURNO                      
                      DIST-JAN90                       900123     
----ENDF/B-VI         MATERIAL  828                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC             
 *         *          *          *          *          *         *
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  DOCUMENTATION INCLUDED IN EPRI-NP-973 1978 ALAPOUR ET.AL.       
 **************************************************************** 
   THERMAL CROSS SECTIONS                                         
            N,GAMMA=3.8 MB+/-20PC CALCULATED BY S.F.MUGHABGHAB    
         (MU78) USING METHOD OF LANE + LYNN (SEE DOCUMENT)        
            N,ALPHA=235 MILLIBARNS WEIGHTED AVERAGE OF(HA61),     
                                  (SE56),(MA47).                  
            N,ABSORPTION=238.8 MB. TOTAL OF ABOVE.                
         THESE CROSS SECTIONS ASSUMED TO BE I/V TO APPROX 100KEV. 
 **************************************************************** 
  SINCE VIRTUALLY NO EXPERIMENTAL DATA AVAILABLE,THIS EVALUATION  
  IS ALMOST TOTALLY CALCULATED WITH NUCLEAR MODEL CODES.          
 **************************************************************** 
   MF=2 MT=151 NO RESONANCE PARAMETER DATA AVAILABLE.SMOOTH CROSS 
       SECTIONS CALCULATED IN THE RESONANCE REGION CONSTRUED AS   
       "AVERAGE"CROSS SECTIONS.                                   
 **************************************************************** 
   MF=3 MT=1 TOTAL CROSS SECTION IS CALCULATED AS SUM OF THE CROSS
       SECTIONS LISTED BELOW.IN GOOD AGREEMENT WITH PRELIMINARY   
       MEASUREMENTS BY AUCHAMPAUGH(AU77).                         
   **** MT=2 TOTAL ELASTIC CROSS AT LOW ENERGY DERIVED FROM       
       EXP.MEASURED COHERENT SCATTERING AMPLITUDE. (VA68) HIGH    
       ENERGY CROSS SECTION CALCULATED WITH NUBAK (AN IN-HOUSE    
       VERSION OF"ABACUS")(AU64)                                  
   **** MT=4 DERIVED FROM THE SUMMATION OF MT=51-62 AND MT=91     
   **** MT=51-62,91 THESE LEVELS CALCULATED WITH NUCLEAR MODEL    
       CODES "MODNEW"(AN IN-HOUSE VERSION OF UHL'S CODE)(UH72)    
       MODIFIED FOR GILBERT AND CAMERON PARAMETERS(SEE DOCUMENT   
       ABOVE) AND"COMNUC" (DU70). COMNUC RESULTS NORMALIZED TO    
       HIGH ENERGY MODNEW RESULTS TO ALLOW FOR COMPETING REACTIONS
   **** MT=16 CALCULATED WITH"MODNEW"(UH72) NO NORMALIZATION      
       AVAILABLE.                                                 
   **** MT=22 CALCULATED WITH"MODNEW"(UH72) NO NORMALIZATION      
       AVAILABLE.                                                 
   **** MT=28 CALCULATED WITH"MODNEW"(UH72) NO NORMALIZATION      
       AVAILABLE.                                                 
   **** MT=102 CALCULATED WITH"COMNUC"(DU70).LEVEL SPACING ASSUMED
       AND GAMMA GAMMA ASSUMED.2PI GAMMA GAMMA OVER D =0.000063.  
       CROSS SECTION AT 14.0 MEV=0.1MILLIBARN.                    
   **** MT=103 CALCULATED WITH"MODNEW"(UH72).NEUTRON YIELD        
       ACTIVATION MEASUREMENT AT 14.1 MEV=21.5+-1.7 MILLIBARNS BY 
       MENLOVE (ME70) SUPPORTS CALCULATION VALUE 14.1MEV=40 MILLI-
       BARNS.                                                     
   **** MT=104 CALCULATED WITH"MODNEW(UH72) NO NORMALIZATION      
       AVAILABLE.                                                 
   **** MT=107 N,ALPHA CROSS SECTION EXOERGIC.CALCULATED WITH     
       "MODNEW"(UH72).NO NORMALIZATION AVAILABLE.CALCULATIONS BY  
       ARTHUR(AR77) WITH LASL VERSION OF"COMNUC" SHOW SIMILAR     
       SHAPE AND MAGNITUDE.                                       
 **************************************************************** 
   MF=4 MT=2 ELASTIC ANGULAR DISTRIBUTIONS CALCULATED WITH"NUBAK" 
       AS A KLASS 3 PROBLEM(AU64)                                 
   **** MT=16,22,28,91 GIVEN AS ISOTROPIC IN LAB SYSTEM           
   **** M=51-62 GIVEN AS ISOTROPIC IN THE C.O.M. SYSTEM           
 **************************************************************** 
   MF=5 MT=16,22,28,91 TEMPERATURE DISTRIBUTIONS AS A FUNCTION OF 
       ENERGY CALCULATED PER PRESCRIPTION OF GILBERT AND CAMERON  
       (GI65)                                                     
 **************************************************************** 
       AJ77 F.AJZENBERG-SELOVE ENERGY LEVELS OF LIGHT NUCLEI      
                      A=18 PPP1-77   FEB.1977                     
                      A=16-17 NUC.PHYS.A281,1,1977                
                      A=13-15 NUC.PHYS.A268,1,1976                
                      A=11-12 NUC.PHYS.A248,1,1975                
                      A= 5-10 NUC.PHYS.A227,1,1974                
       AR77 E.ARTHUR      LASL PRIVATE COMM. 1977                 
       AU77 G.AUCHAMPAUGH LASL PRIVATE COMM. 1977                 
       AU64 E.H.AUERBACH,ABACUS-2 BNL 6562 1964                   
       BA70 H.BABA NUC.PHYS.A159,625,1970                         
       BA66 J.K.BAIR ET.AL. PHYS.REV.144,799,1966                 
       BE74 I.BERGQVIST PROC.2ND INT SYMP ON NEUTRON CAPTURE GAMMA
                      RAY SPECTROSCOPY AND RELATED TOPICS,199,1974
       DU70 C.L.DUNFORD,COMNUC AI-AEC-12931,1970                  
       FE   E.FERMI NUCLEAR PHYSICS U.OF CHI PRESS PP-145-146 REV.
                      EDITION                                     
       GI65 A.GILBERT AND A.G.W.CAMERON,CAN.J.PHYS.43,1446,1965   
       GR50 A.E.S.GREEN AND D.F.EDWARDS PHYS.REV.91,49,1952       
       HA61 G.C.HANNA ET.AL.CAN.J.PHYS.39,1784,1961               
       HO72 N.E.HOLDEN AND W.F.WALKER,G.E.CHART OF NUCLIDES 11TH  
                      ED.REVISED TO 1972                          
       MA47 A.N.MAY AND E.P.HINCKS CAN.J.RES.A25,77,1947          
       MA50 M.G.MAYER PHYS.REV.78,77,1960                         
       MC77 A.B.MCDONALD ET.AL.NUC.PHYS.A281,325,1977             
       ME70 H.O.MENLOVE ET.AL. NSE 40,136,1970                    
       MO70 G.L.MORGAN ET.AL. NUC.PHYS.148,480,1970               
       MU78 S.F.MUGHABGHAB PC-78 METHOD BNL-NCS25086R(TBP PHY.LET)
       MU73 S.F.MUGHABGHAB AND D.I.GARBER BNL-325 3RD ED.VOLI 1973
       PE74 C.M.PEREY AND F.G.PEREY AT.DATA TABLES 13,293,1974    
       RO77 P.ROSE BNL PRIV.COMM. 1977                            
       SE56 E.J.SEPPI  HANFORD PRIV.COMM TO SIGMA CNTR 1956       
       UH72 M.UHL NUC.PHYS.A184,253,1972                          
       VA68 T.M.VALENTINE AERE-R5770,1968                         
       VO69 H.K.VONACH AND M.HILLE NUC.PHYS.A127,289,1969         
       WI64 D.WILMORE AND P.E.HODGSON NUC.PHYS.55,673,1964        
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