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54-Xe-128 NEA RCOM-JUL82 SCIENTIFIC CO-ORDINATION GROUP
DIST-JAN09 20090105
----JEFF-311 MATERIAL 5437
-----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 ENDF/B-V(MAT=1348). *
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* 27-APR-89: MISSING CHARGE PARTICLE PRODUCTION DATA INCLUDED
* FROM REAC-ECN-4 LIBRARY
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BNL EVAL-MAR78 M.R.BHAT AND S.F.MUGHABGHAB
DIST-APR79 REV0-MAR78 780412
THIS EVALUATION IS THE SAME AS IN ENDF/B-IV(MAT=1172)
EXCEPT FOR CHANGES IN THE FOLLOWING MF/MTS - 2/151,3/1,
3/2,3/16,3/102,3/103,5/17
DATA USED
2200 M/SEC CAPTURE CROSS-SECTION 5.36B.THIS WAS OBTAINED BY
TAKING 0.36B FOR THE CROSS-SECTION TO THE METASTABLE
STATE WHICH IS A MEAN OF 0.29B BY E.KONDAIAH ET.AL.
NP/A120,329(1968) AND 0.43B BY TILBURY ET.AL,NSE31,545
(1968) AND ADDING 5B MEASURED BY MACNAMARA AND THODE
PHYS.REV.80,296(1950) TO THE GROUND STATE
RESOLVED RESONANCE PARAMETERS BY P.RIBON,THESIS,UNIVERSITY OF
PARIS,JAN16,1969. 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 1.814B
AT 14.5MEV WHICH IS A MEAN OF THE DATA OF E.KONDAIAH ET
AL.NP/A120,337(1968) AND SIGG.ET.AL,NSE 60,235(1976)
(N,P) CROSS-SECTION CALCULATED USING FASCRO NORMALISED TO 28MB
AT 14.6MEV AS MEASURED BY SIGG ET.AL.NSE 60,235(1976)
PARTICLE THRESHOLD ENERGIES CALCULATED USING THE DATA OF
A.H.WAPSTRA AND N.B.GOVE,NUCLEAR DATA TABLES VOL9A,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
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