![]() |
|
Back
58-Ce-142 NEA RCOM-JUL83 H.GRUPPELAAR,E.MENAPACE JEF/DOC-30 DIST-JAN09 20090105 ----JEFF-311 MATERIAL 5843 -----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 ** ** ** ****************************************************************** ***************************** JEFF-3.0 *********************** DATA TAKEN FROM :- JEF-2.2 (DIST-JAN92) ****************************************************************** * JEF-2 * * DATA WERE TAKEN FROM CNEN/CEA (MAT=5842) AND TRANSLATED * * TO ENDF/B-V FORMAT AT THE NEA DATA BANK . * ****************************************************************** * 16-FEB-85: DATA EXTENDED UP TO 20 MEV. * 13-OCT-87: CHANGE OF THE FLAG FROM SINGLE LEVEL TO MULTI LEVEL * BREIT-WIGNER RESONANCE PARAMETERS * 27-APR-89: MISSING CHARGE PARTICLE PRODUCTION DATA INCLUDED * FROM REAC-ECN-4 LIBRARY * 1-NOV-90: ADDITIONAL COMMENTS INSERTED ****************************************************************** **************************************************************** * * * MODIFICATIONS FOR JEF-2 58-CE-142 * * * **************************************************************** * * * COOPERATION ECN-PETTEN AND NEA DATA BANK * * H.A.J. VAN DER KAMP - ECN * * H.GRUPPELAAR - ECN * * I.FOREST - NEADB * * C.NORDBORG - NEADB * * * **************************************************************** * RESOLVED RESONANCE REGION: * **************************************************************** * * * THE ORIGINAL JEF-1 EVALUATION HAS BEEN MAINTAINED. * * * * EL=10-5 EV, EH=4.880 KEV. * * * **************************************************************** * THERMAL VALUES (2200M/S): * **************************************************************** * * * CALCULATED VALUES: * * MT=2 SIGMA = 3.77000 B * * MT=102 SIGMA = 0.90000 B * * MT=102 RESONANCE INTEGRAL = 1.01462 B * * * * EXPERIMENTAL VALUES: * * MT=2 SIGMA = NOT AVAILABLE * * MT=102 SIGMA = 0.95 +- 0.05 B * * MT=102 RESONANCE INTEGRAL = 1.15 +- 0.05 B * * * **************************************************************** * REFERENCES: * **************************************************************** * * * 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 * * * **************************************************************** CNEN EVAL APR76 CNEN-CDC-BOLOGNA CERIUM-142 NEUTRON CROSS SECTION EVALUATION -----------------------------MF 1------------------------------- MT 451 2200 M/SEC CAPTURE 0.9B RESONANCE INTEGRAL 0.97B -----------------------------MF 2------------------------------ MT 151 CONTAINS RESOLVED PLUS UNRESOLVED MEAN PARAMETERS -----------------------------MF 3------------------------------- MT 1,2 AND 102 THE BACKGROUND INCLUDES A 1/V RANGE MT 251,252,253 COMPUTED BY SYSMF FROM CERBERO ANGULAR DISTRIBUTIONS. -----------------------------MF 4------------------------------- MT 2 TRANSFORMATION MATRIX COMPUTED BY SYSMF FROM AMSTER. LEGENDRE EXPANSION COEFFICIENTS COMPUTED BY SYSMF FROM CERBERO MT 16 ASSUMED ISOTROPIC IN THE LABORATORY FRAME OF REFERENCE MT 17 ASSUMED ISOTROPIC IN THE LABORATORY FRAME OF REFERENCE MT 91 AND DISCRETE LEVELS ASSUMED ISOTROPIC IN THE LABORATORY FRAME OF REFERENCE -----------------------------MF 5------------------------------- MT 16 EVAPORATION SPECTRUM (LF=9) ASSUMED, WITH T=T(E) AND T = CONSTANT FOR THE 2ND NEUTRON MT 17 EVAPORATION SPECTRUM (LF=9) ASSUMED, WITH T=T(E) AND T = CONSTANT FOR THE 2ND AND THE 3RD NEUTRON MT 91 EVAPORATION SPECTRUM (LF=9) ASSUMED, WITH T=T(E) ---------------------------------------------------------------- COMPUTER CODES USED WERE 1)-CRESO RESONANCE REGION DATA 2)-CERBERO CONTINUUM REGION CROSS SECTION,ANGULAR AND ENERGY DISTRIBUTION DATA 3)-ERINNI HIGH ENERGY REGION CROSS SECTIONS 4)-SYSMF DATA HANDLING AND FILE GENERATION COMPLETED ON MONDAY 5 APRIL 1976 AT 15.46.29 ***************** PROGRAM LINEAR (VERSION 83-1) ***************** DATA LINEARIZED TO WITHIN AN ACCURACY OF 0.100 PER-CENTBack |