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5.412600+4 1.248230+2 1 0 2 0
0.000000+0 0.000000+0 0 0 0 6
1.000000+0 2.000000+7 0 0 10 31
0.000000+0 0.000000+0 0 0 59 1
54-Xe-126 NEA RCOM-JUL82 SCIENTIFIC CO-ORDINATION GROUP
DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 5431
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
***************************** 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 ENDF/B-V(MAT=1339). *
******************************************************************
* 27-APR-89: MISSING CHARGE PARTICLE PRODUCTION DATA INCLUDED
* FROM REAC-ECN-4 LIBRARY
******************************************************************
BNL EVAL-MAR78 M.R.BHAT AND S.F.MUGHABGHAB
DIST-APR79 REV0-MAR78 780720
THIS EVALUATION IS THE SAME AS IN ENDF/B-IV(MAT=1171)
EXCEPT FOR CHANGES IN THE FOLLOWING MF/MTS - 2/151,3/1,
3/2,3/16,3/102,5/17
DATA USED
2200 M/SEC CAPTURE CROSS-SECTION SET AT 2.2B A VALUE OBTAINED BY
M.BRESESTI ET.AL.J.INORG.NUCL.CHEM.27,1175(1965)
RESOLVED RESONANCE PARAMETERS BY P.RIBON,THESIS,UNIVERSITY OF
PARIS,JAN16,1969
THE TWO RESONANCES AT 86.56 AND 100.17EV ARE TAKEN FROM
THE LIST OF UNASSIGNED RESONANCES IN RIBONS THESIS AND
ASSIGNED TO XE-126. BOUND LEVEL PARAMETERS ADJUSTED TO
GIVE THE ASSIGNED THERMAL CAPTURE CROSS-SECTION.
MEV TOTAL CROSS-SECTION OF NATURAL XENON BY F.J.VAUGHN ET.AL.
PHYS.REV.118,683,1960
(N,2N) CROSS-SECTION CALCULATED FROM FASCRO NORMALISED TO 1.481B
AT 14.5MEV WHICH IS A MEAN OF THE DATA OF E.KONDAIAH ET
AL.NP/A120,337(1968) AND SIGG ET.AL.NSE60,235(1976)
PARTICLE THRESHOLD ENERGIES CALCULATED USING THE DATA OF
A.H.WAPSTRA AND N.B.GOVE,NUCLEAR DATA TABLES VOLA9,267,
1971
NUCLEAR MODEL CALCULATIONS
OPTICAL MODEL PARAMETERS WILMORE-HODGSON PARAMETERS P.E.HODGSON
ANN.REV.NUCL.SCI.VOL17,1,1967 R0=1.26FM.
CODES USED
1.ABACUS-2 E.H.AUERBACH BNL6562,1964
TOTAL AND SHAPE-ELASTIC CROSS-SECTIONS
2.COMMNUC(AI-AEC-12931)C.DUNFORD. COMPOUND NUCLEUS
REACTION CROSS SECTIONS.
3.FASCRO(TO BE PUBLISHED)S.PEARLSTEIN,(N,PARTICLE)CROSS
SECTIONS.
4.CHAD(NAA-SR-11231)R.F.BERLAND. ANGULAR DISTRIBUTION
DATA FITTED BY USING THIS CODE.
NUCLEAR TEMPERATURE CALCULATIONS BASED ON GILBERT AND CAMERON
CAN.JOUR.PHYS.VOL43,1446,1965
1 451 64
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