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 60-Nd-145 NEA        RCOM-JUL83 H.GRUPPELAAR,E.MENAPACE          
 JEF/DOC-30           DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 6034                               
-----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 RCN-3 EVALUATION (MAT=6045).          *
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*   16-AUG-84: FORMAT CORRECTIONS PERFORMED.                      
*   16-FEB-85: NEW BACKGROUND CROSS SECT. CALCULATED AND INSERTED 
*    7-MAR-85: Q-VALUES FOR MT=102,107 CORRECTED                  
*   17-OCT-86: RESONANCE PARAMETER SECTION UPDATED USING DATA    *
*              FROM THE 4TH ED. OF BNL-325.                      *
*   27-APR-89: MISSING CHARGE PARTICLE PRODUCTION DATA INCLUDED   
*              FROM REAC-ECN-4 LIBRARY                            
*    1-NOV-90: ADDITIONAL COMMENTS INSERTED                       
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 *                                                              * 
 *   MODIFICATIONS FOR JEF-2       60-ND-145                    * 
 *                                                              * 
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 *                                                              * 
 *   COOPERATION ECN-PETTEN AND NEA DATA BANK                   * 
 *   H.A.J. VAN DER KAMP - ECN                                  * 
 *   H.GRUPPELAAR        - ECN                                  * 
 *   I.FOREST            - NEADB                                * 
 *   C.NORDBORG          - NEADB                                * 
 *                                                              * 
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 *   RESOLVED RESONANCE REGION:                                 * 
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 *                                                              * 
 *   RESOLVED RESONANCE PARAMETERS WERE REPLACED BY DATA FROM   * 
 *   MOST RECENT BROOKHAVEN COMPILATION(MU81).                  * 
 *                                                              * 
 *   EL=10-5 EV, EH=2.166 KEV.                                  * 
 *                                                              * 
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 *   THERMAL VALUES (2200M/S):                                  * 
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 *                                                              * 
 *   CALCULATED VALUES:                                         * 
 *   MT=2    SIGMA              =  18.2618 B                    * 
 *   MT=102  SIGMA              =  41.8510 B                    * 
 *   MT=102  RESONANCE INTEGRAL = 231.575  B                    * 
 *                                                              * 
 *   EXPERIMENTAL VALUES:                                       * 
 *   MT=2    SIGMA              = NOT AVAILABLE                 * 
 *   MT=102  SIGMA              =  42 +-  2 B                   * 
 *   MT=102  RESONANCE INTEGRAL = 240 +- 35 B                   * 
 *                                                              * 
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 *   REFERENCES:                                                * 
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 *                                                              * 
 *   MU81: MUGHABGHAB,S.F., M.DIVADEENAM, N.E.HOLDEN            * 
 *         NEUTRON CROSS SECTIONS VOLUME 1                      * 
 *         NEUTRON RESONANCE PARAMETERS AND THERMAL CROSS       * 
 *         SECTIONS, PART A, Z=1-60, ACADEMIC PRESS 1981        * 
 *                                                              * 
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      ORIGINAL DATA IN KEDAK FORMAT WERE TRANSLATED INTO ENDF/B   
      FORMAT WITH KTOE-3.                                         
                                                                  
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    EVAL. FOR:      NEODYMIUM    -   145        DISTR:   JUL  78  
                                                                  
ORIGINAL COMMENT IS:                                              
                                                                  
$RCN 2.3 EVALUATION H.GRUPPELAAR       ND145X     24/07/78  $     
 N,P N,D N,T N,HE3 N,A ADDED (THRES-2), ABS AND TOTAL CORRECT REV 
 MINIMUM ENERGY                        .00100    EV               
 MIN EN OF STATISTICAL MODEL          2.16646   KEV               
 ENERGY OF FIRST EXCITED STATE       67.20000   KEV               
 CONTINUOUS STAT MODEL ABOVE          1.16120   MEV               
 HIGH ENERGY MODEL ABOVE              6.50000   MEV               
 MAXIMUM ENERGY                      15.00000   MEV               
 LEVEL DENSITY PARAMETER  ND145      20.42000 1/MEV               
 LEVEL DENSITY PARAMETER  ND144      17.60000 1/MEV               
 *****ADJUSTED EVALUATION BASED ON STEK INTEGRAL DATA*****        
 *****OTHER DIFFERENCE: S0 ACCORDING TO MUSGROVE ET AL. (MU77)    
 RESOLVED ENERGY REGION UPTO 2.16 KEV                             
      EVALUATION WITH SIGMA-2 AT 0 K, MULTILEVEL FORMULA          
      RESOLVED RESONANCES EVALUATED BY RIBON ET AL.(RI75)         
      ALL RESONANCES HAVE BEEN ASSIGNED L=0                       
      FOR RESONANCES WITH UNKNOWN CAPTURE WIDTH THE VALUE 86 MV (M
      HAS BEEN INSERTED.                                          
      NEGATIVE RESONANCE PARAMETERS HAVE BEEN FITTED TO FIT THE   
      CAPTURE (MU73) AND SCATTERING (VE73) CROSS SECTIONS AT 0.025
 STRENGTH FUNCTION REGION UPTO 50 KEV                             
      CAPTURE CROSS SECTIONS WITH CODE FISPRO-ECN                 
      OTHER CROSS SECTIONS WITH CODE SASSI-ECN                    
      S-WAVE STRENGTH FUNCTION, S0=5.2 (MU77)                     
      P-WAVE STRENGTH FUNCTIOM, S1=0.98                           
      S-WAVE CAPTURE WIDTH= 89 MV                                 
      P-WAVE CAPTURE WIDTH= 88 MV                                 
      DOBS= 18.6 EV                                               
 HIGH ENERGY REGION                                               
      ALL CROSS SECTIONS WITH CODE SASSI-ECN                      
      OPTICAL MODEL FROM IGARASI ET AL. (IG75)                    
      LEVEL SCHEME OF TARGET NUCLEUS FROM HILLIS ET AL.(HI75)     
      AND FROM GALES ET AL.(GA73)                                 
 ***************** PROGRAM LINEAR (VERSION 83-1) *****************
 DATA LINEARIZED TO WITHIN AN ACCURACY OF     0.100 PER-CENT      
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