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54-Xe-134 NEA RCOM-JUL82 H.GRUPPELAAR,E.MENAPACE
JEF/DOC-30 DIST-JAN09 20090105
----JEFF-311 MATERIAL 5455
-----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=1354). *
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* 22-DEC-87: RES 450 EV REMOVED
* 27-APR-89: MISSING CHARGE PARTICLE PRODUCTION DATA INCLUDED
* FROM REAC-ECN-4 LIBRARY
* 30-JUN-89: FOR MF=3 MT=102 THE CROSS SECTIONS BETWEEN 11 MEV
* AND 20 MEV HAS BEEN CHANGED FROM 0 TO 1.0E-08
* 1-NOV-90: ADDITIONAL COMMENTS INSERTED
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* *
* MODIFICATIONS FOR JEF-2 54-XE-134 *
* *
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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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* *
* THE ORIGINAL JEF-1 EVALUATION HAS BEEN MAINTAINED, *
* HOWEVER THE RESONANCE OF 450 EV HAS BEEN REMOVED FROM *
* IT. *
* *
* EL=10-5 EV, EH=2.000 KEV. *
* *
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* THERMAL VALUES (2200M/S): *
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* *
* CALCULATED VALUES: *
* MT=2 SIGMA = 4.34627 B *
* MT=102 SIGMA = 0.249380 B *
* MT=102 RESONANCE INTEGRAL = 0.630614 B *
* *
* EXPERIMENTAL VALUES: *
* MT=2 SIGMA = NOT AVAILABLE *
* MT=102 SIGMA = 0.265 +- 0.020 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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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=1177)
EXCEPT FOR CHANGES IN THE FOLLOWING MF/MTS - 2/151,3/1,
3/2,3/102,3/103,5/17
DATA USED
2200 M/SEC CAPTURE CROSS SECTION 0.25B. THIS IS A MEAN OF THE
VALUE OF 0.265+-0.020B BY E.KONDAIAH ET.AL NP A120,329,
1968 AND 0.228+-0.020B BY T.A.EASTWOOD ET.AL.EANDC(CAN)
16,6,1963.
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 IS AS GIVEN BY FASCRO SINCE THE EXPERIMENTAL
DATA BY E.KONDAIAH ET.AL.NPA/120,337,1968 AND BY SIGG
ET.AL.NSE.60,235(1976) ARE DISCREPANT
(N,P) CROSS-SECTION CALCULATED FROM FASCRO NORMALISED TO 2.1MB AT
14.5MEV WHICH IS A MEAN OF THE DATA OF KONDAIAH ET.AL.
AND OF SIGG ET.AL.
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
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