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5.413200+4 1.307710+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 0 112 1
54-Xe-132 NEA RCOM-JUL82 H.GRUPPELAAR,E.MENAPACE
JEF/DOC-30 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 5449
-----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=1352). *
******************************************************************
* 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 THE SECTION MF=3 MT=102 THE CROSS SECTIONS BET-*
* WEEN 11 MEV AND 20MEV CHANGED FROM 0 TO 1.0E-08 *
* 1-NOV-90: ADDITIONAL COMMENTS INSERTED
******************************************************************
****************************************************************
* *
* MODIFICATIONS FOR JEF-2 54-XE-132 *
* *
****************************************************************
* *
* 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=4.255 KEV. *
* *
****************************************************************
* THERMAL VALUES (2200M/S): *
****************************************************************
* *
* CALCULATED VALUES: *
* MT=2 SIGMA = 3.75187 B *
* MT=102 SIGMA = 0.448616 B *
* MT=102 RESONANCE INTEGRAL = 1.58890 B *
* *
* EXPERIMENTAL VALUES: *
* MT=2 SIGMA = NOT AVAILABLE *
* MT=102 SIGMA = 0.450 +- 0.060 B *
* MT=102 RESONANCE INTEGRAL = 4.6 +- 0.6 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 *
* *
****************************************************************
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=1176)
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 0.44B. MEAN OF THE CAPTURE
CROSS-SECTION TO THE METASTABLE STATE BY EASTWOOD ET.
AL.EANDC(CAN)-16(1963) AND OF KONDAIAH ET.AL.NPA/120,
329(1968) IS 26MB. KARDON,YF,10,27(1969) OBTAINS FOR
THE RATIO SIGMA(METASTABLE)/SIGMA(GROUND) = 0.063.IF
THIS RATIO IS USED WITH THE ABOVE VALUE OF 26MB ONE
OBTAINS SIGMA(GROUND)=413MB.MEAN OF THIS AND KONDAIAH
VALUE OF 415MB IS 414MB WHICH ADDED TO 26MB GIVES 0.44B
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,P) CROSS-SECTION CALCULATED USING FASCRO NORMALISED TO 3.3MB
AT 14.5MEV. THIS IS A MEAN OF THE DATA OF E.KONDAIAH ET
AL. NP/A120,329(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 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
1 451 117
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