60-Nd-143 NEA RCOM-JUL82 H.GRUPPELAAR,E.MENAPACE
JEF/DOC-30 DIST-JAN09 20090105
----JEFF-311 MATERIAL 6028
-----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)
Increase by 4% of g_n for the bound level
Recommendation C. Chabert et al. JEF/DOC-885
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* JEF-2 *
* DATA WERE TAKEN FROM ENEA EVALUATION (MAT=6043). *
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* 19-JUL-84: NEW VERSION FROM ENEA COMPILED.
* 16-FEB-85: DATA EXTENDED UP TO 20 MEV.
* 18-AUG-88: RESONANCES ADDED
* 27-APR-89: MISSING CHARGE PARTICLE PRODUCTION DATA INCLUDED
* FROM REAC-ECN-4 LIBRARY
* 21-NOV-89: INSERTION OF BACKGROUND CURVE WHICH ACCOUNTS FOR
* MISSED RESONANCES IN THE RESOLVED RANGE IN MF=3
* (MT=1 AND MT=102) BY ECN. EXTENSION TO 20 MEV
* IMPROVED BY ECN.
* 1-NOV-90: A FEW NEW RESOLVED RESONANCES ADDED AND ADDITIONAL
* COMMENTS INSERTED
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* *
* MODIFICATIONS FOR JEF-2 60-ND-143 *
* *
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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). *
* *
* FOR THOSE RESONANCES FOR WHICH GN AND GG VALUES ARE *
* UNKNOWN, AN AVERAGE VALUE FOR GG HAS BEEN ASSUMED AND *
* GN WAS DERIVED FROM THIS AVERAGE VALUE AND THE CAPTURE *
* AREA AS GIVEN IN MU81. *
* *
* INSERTION OF SMOOTH BACKGROUND CURVE WHICH ACCOUNTS FOR *
* MISSED RESONANCES IN THE RESOLVED RESONANCE RANGE IN *
* MF3(MT=1 AND MT=102) HAS BEEN PERFORMED BY ECN. *
* *
* EXTENSION TO 20 MEV HAS BEEN IMPROVED. *
* *
* EL=10-5 EV, EH=5.521 KEV. *
* *
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* THERMAL VALUES (2200M/S): *
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* *
* CALCULATED VALUES: *
* MT=2 SIGMA = 80.4193 B *
* MT=102 SIGMA = 323.075 B *
* MT=102 RESONANCE INTEGRAL = 129.762 B *
* *
* EXPERIMENTAL VALUES: *
* MT=2 SIGMA = 80 +- 2 B *
* MT=102 SIGMA = 325 +- 10 B *
* MT=102 RESONANCE INTEGRAL = NOT AVAILABLE *
* *
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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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60-ND-143 CNEN EVAL MAY79 CNEN-CDC-BOLOGNA
NEODYMIUM-143 NEUTRON CROSS SECTION EVALUATION
NEUTRON CROSS SECTION EVALUATION BY CNEN - BOLOGNA
-----------------------------MF 1-------------------------------
MT 451
2200 M/SEC CAPTURE 317B
RESONANCE INTEGRAL 125B
-----------------------------MF 2------------------------------
MT 151
CONTAINS RESOLVED PLUS UNRESOLVED MEAN PARAMETERS
-----------------------------MF 3-------------------------------
MT 1,2 AND 102
CONTAIN A SMOOTH BACKGROUND TO BE ADDED TO THE RESONANCE
CONTRIBUTION TO ACCOUNT FOR NEGATIVE PEAKS IN THE SCATTERING
CROSS SECTION AND FOR LOSS RESONANCES CONTRIBUTION.
MT 251,252,253
COMPUTED BY SYSMF FROM CERBERO ANGULAR DISTRIBUTIONS.
-----------------------------MF 4-------------------------------
MT 2
TRANSFORMATION MATRIX AND LEGENDRE COEFFICIENTS COMPUTED BY
SYSMF FROM THE ANGULAR DISTRIBUTIONS GENERATED BY CERBERO.
MT 16, 51 TO 79 AND 91
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 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 WEDNESDAY 23 MAY 1979 AT 14.48.14
***************** PROGRAM LINEAR (VERSION 83-1) *****************
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