NEA Data Bank
Back

 93-Np-238 NEA        RCOM-JUN82 SCIENTIFIC CO-ORDINATION GROUP   
                      DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 9349                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
***************************  JEFF-3.1.1  *************************
**                                                              **
**         Original data taken from:  JEFF-3.1                  **
**                                                              **
******************************************************************
*****************************  JEFF-3.1  *************************
**                                                              **
**         Original data taken from:  JEFF-3.0                  **
**                                                              **
******************************************************************
                                                                  
  05-01 NEA/OECD (Rugama) 8 delayed neutron groups                
  Jefdoc-976 (Wilson and England, Prog Nucl Eng 41,71(2002)       
                                                                  
                                                                  
*****************************   JEFF-3.0   ***********************
                                                                  
   DATA TAKEN FROM   :-   JEF-2.2 (DIST-JAN92)                    
                                                                  
                          ENDF/B-VI.4 (MF1MT452,455,456 MF5MT455) 
                                                                  
******************************************************************
******************************************************************
*   JEF-2                                                        *
*     DATA WERE TAKEN FROM ENDF/B-V(MAT=8338).                   *
******************************************************************
*   21-DEC-84: RADIOACTIVE DECAY DATA DELETED.                    
*   28-AUG-85: MISSING ISOTROPIC ANG. DISTR. FOR FISSION INSERTED 
*   30-OCT-86: CROSS SECTION DATA ABOVE 10 KEV AND ALL MT=4,16,17 
*              AND 91 REPLACED BY DATA FROM THE ENDL84 LIBRARY.   
*    5-APR-88: CHANGE OF THE FLAG FROM SINGLE LEVEL TO MULTI LEVEL
*              BREIT-WIGNER RESONANCE PARAMETERS.FOR THE SPIN OF  
*              L=0,RESONANCES HAVE BEEN RANDOMLY ASSIGNED BY THE  
*              COMPUTER CODE RNDSPIN (H. GRUPPELAAR)              
******************************************************************
                                                                  
           SRL        EVAL-AUG75-BENJAMIN AND MCCROSSON           
                      DIST-DEC78                       790307     
 FILES CONVERTED TO ENDF/B-V FORMAT AND DECAY DATA MERGED AT      
 BNL BY R. KINSEY                                                 
*          *          *          *          *          *          
 NEPTUNIUM-238 EVALUATION AUGUST 1975 - R.W.BENJAMIN AND          
                                        F.J.MCCROSSON AT SRL      
MF=1                  GENERAL INFORMATION                         
  MT=452 NUBAR   THERMAL VALUE COMPUTED FROM SEMI-EMPIRICAL WORK  
     OF GORDEEVA AND SMIRENKIN(REF.1) AS REVISED BY MANERO AND    
     KONSHIN(REF.2).  ENERGY DEPENDENCE BASED ON WORK OF HOWER-   
     TON(REF.3).                                                  
MF=2                  RESONANCE PARAMETERS(0 TO 10 KEV)           
  MT=151 RESOLVED RESONANCES   RESONANCE PARAMETERS DETERMINED BY 
     THE GENRPAR CODE(REF.4) BASED UPON THE SRL DATA SET AND AN   
     AVERAGE LEVEL SPACING OF 1.05 EV.  RESOLVED REGION - 0 TO    
     100.2 EV.                                                    
         UNRESOLVED RESONANCES   SAME BASIS AS RESOLVED WITH      
     AVERAGE RESONANCE PARAMETERS.  UNRESOLVED REGION - 100.2 EV  
     TO 10 KEV.                                                   
CROSS SECTION         SIGMA(0.0253 EV)      I(0.5 EV - 20 MEV)    
TOTAL                  2250.99                                    
ELASTIC                  21.25                                    
FISSION                2026.90                895.60              
CAPTURE                 202.83                100.03              
MF=3                  SMOOTH CROSS SECTIONS(0 TO 20 MEV)          
  ***    THE DATA IN FILE 3 ARE GIVEN ONLY SO THAT THE VARIOUS    
     PROCESSING CODES CAN WORK.  CONTINUITY WITH THE UNRESOLVED   
     REGION IS PROVIDED, BUT THE CROSS SECTIONS DROP IMMEDIATELY  
     TO ZERO.  THE ELASTIC SCATTERING CROSS SECTION ABOVE 10 KEV  
     IS THE POTENTIAL SCATTERING CROSS SECTION CALCULATED WITH A  
     SPHERICAL OPTICAL MODEL POTENTIAL AT 10 KEV.                 
MF=4                ANGULAR DISTRIBUTIONS                         
  MT=2                   ELASTIC                                  
     DISTRIBUTIONS TAKEN FROM ENDF/B-V U-238                      
MF=5                  SECONDARY NEUTRON ENERGY DISTRIBUTIONS      
  MT=18 FISSION   SIMPLE FISSION MAXWELLIAN WITH ENERGY-DEPENDENT 
     TEMPERATURE.                                                 
                      REFERENCES                                  
  1. L.D.GORDEEVA AND G.N.SMIRENKIN,SOV.AT.EN.14(1963)56.         
  2. F.MANERO AND V.A.KONSHIN,AT.EN.REV.10(1972)637.              
  3. R.J.HOWERTON,NUCL.SCI.ENG.46(1971)42.                        
  4. F.J.MCCROSSON,PROC.CONF.NEUT.CROSS SECTIONS AND TECH.,       
     KNOXVILLE,TN,MARCH 1971,P.714.                               
******************************************************************
                                                                  
 Relevant comments from ENDF/B-VI.4                               
 ----------------------------------                               
                                                                  
 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC             
 *         *          *          *          *          *         *
 FILES CONVERTED TO ENDF/B-V FORMAT AND DECAY DATA MERGED AT      
 BNL BY R. KINSEY                                                 
*          *          *          *          *          *          
 NEPTUNIUM-238 EVALUATION AUGUST 1975 - R.W.BENJAMIN AND          
                                        F.J.MCCROSSON AT SRL      
                                                                  
MF=1                  GENERAL INFORMATION                         
  MT=452 NUBAR   THERMAL VALUE COMPUTED FROM SEMI-EMPIRICAL WORK  
     OF GORDEEVA AND SMIRENKIN(REF.1) AS REVISED BY MANERO AND    
     KONSHIN(REF.2).  ENERGY DEPENDENCE BASED ON HOWERTON (REF.3) 
  MT=455 DEL. NUBAR, M.C.BRADY AND T.R.ENGLAND, NSE 103,129(1989) 
                                                                  
MF=5                  SECONDARY NEUTRON ENERGY DISTRIBUTIONS      
  MT=455 DEL. NUBAR, M.C.BRADY AND T.R.ENGLAND, NSE 103,129(1989) 
                      REFERENCES                                  
  1. L.D.GORDEEVA AND G.N.SMIRENKIN,SOV.AT.EN.14(1963)56.         
  2. F.MANERO AND V.A.KONSHIN,AT.EN.REV.10(1972)637.              
  3. R.J.HOWERTON,NUCL.SCI.ENG.46(1971)42.                        
  4. F.J.MCCROSSON,PROC.CONF.NEUT.CROSS SECTIONS AND TECH.,       
     KNOXVILLE,TN,MARCH 1971,P.714.                               
******************************************************************
Back