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54-Xe-132 NEA RCOM-JUL82 H.GRUPPELAAR,E.MENAPACE JEF/DOC-30 DIST-JAN09 20090105 ----JEFF-311 MATERIAL 5449 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT *************************** JEFF-3.1.1 ************************* ** ** ** Original data taken from: JEFF-3.1 ** ** ** ****************************************************************** ***************************** 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.VOL43,1446,1965Back |