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5.413100+4 1.297810+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 0 108 1
54-Xe-131 NEA RCOM-JUL82 H. GRUPPELAAR
DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 5446
-----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=1351). *
******************************************************************
* 16-FEB-85: RESONANCE PARAMETERS REVISED BY H.GRUPPELAAR.
* 24-OCT-86: RESONANCE PARAMETER SECTION UPDATED USING DATA *
* FROM THE 4TH ED. OF BNL-325. *
* 27-APR-89: MISSING CHARGE PARTICLE PRODUCTION DATA INCLUDED
* FROM REAC-ECN-4 LIBRARY
* 30-JUN-89: IN MF=3,MT=102 SECTION,THE CROSS SECTIONS BETWEEN *
* 9 MEV AND 20 MEV CHANGED FROM 0 TO 1.0E-08 *
* 1-NOV-90: ADDITIONAL COMMENTS INSERTED
******************************************************************
****************************************************************
* *
* MODIFICATIONS FOR JEF-2 54-XE-131 *
* *
****************************************************************
* *
* 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: *
****************************************************************
* *
* RESOLVED RESONANCE PARAMETERS WERE REPLACED BY DATA FROM *
* MOST RECENT BROOKHAVEN COMPILATION(MU81). *
* *
* EL=10-5 EV, EH=2.1935 KEV. *
* *
****************************************************************
* THERMAL VALUES (2200M/S): *
****************************************************************
* *
* CALCULATED VALUES: *
* MT=2 SIGMA = 24.3411 B *
* MT=102 SIGMA = 84.9762 B *
* MT=102 RESONANCE INTEGRAL = 895.088 B *
* *
* EXPERIMENTAL VALUES: *
* MT=2 SIGMA =NOT AVAILABLE *
* MT=102 SIGMA = 85 +- 10 B *
* MT=102 RESONANCE INTEGRAL = 900 +- 100 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 *
* *
****************************************************************
54-XE-131 BNL EVAL-MAR78 M.R.BHAT AND S.F.MUGHABGHAB
DIST-NOV84 REVISED H.GRUPPELAAR 841126
THIS EVALUATION IS THE SAME AS IN ENDF/B-V(MAT=1351)
EXCEPT FOR CHANGES IN THE FOLLOWING MF/MTS - 2/151,3/1,
3/2. REVISIONS BY H.GRUPPELAAR, ECN PETTEN
DATA USED (REVISION IN RESOLVED-RESONANCE RANGE)
2200 M/SEC CAPTURE CROSS SECTION 85 B
RESONANCE INTEGRAL FOR CAPTURE CROSS SECTION 891 B
RESOLVED RESONANCE PARAMETERS TAKEN FROM NEWEST BNL-COMPILATON,
ISSUED IN 1981. 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,P) CROSS-SECTION NORMALISED TO 6.2MB 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)
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
1 451 113
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