58-Ce-140 NEA RCOM-JUL82 H. GRUPPELAAR
DIST-JAN09 20090105
----JEFF-311 MATERIAL 5837
-----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= 724). *
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* 16-FEB-85: RESONANCE PARAMETERS REVISED BY H.GRUPPELAAR.
* 27-APR-89: MISSING CHARGE PARTICLE PRODUCTION DATA INCLUDED
* FROM REAC-ECN-4 LIBRARY
* 1-NOV-90: ADDITIONAL COMMENTS INSERTED
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* *
* MODIFICATIONS FOR JEF-2 58-CE-140 *
* *
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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. *
* AVERAGE SPIN VALUES HAVE BEEN REASSIGNED RANDOMLY USING *
* THE COMPUTER CODE RNDSPIN(GRUPPELAAR). *
* *
* EL=10-5 EV, EH=20 KEV. *
* *
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* THERMAL VALUES (2200M/S): *
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* *
* CALCULATED VALUES: *
* MT=2 SIGMA = 3.26370 B *
* MT=102 SIGMA = 0.574474 B *
* MT=102 RESONANCE INTEGRAL = 0.335643 B *
* *
* EXPERIMENTAL VALUES: *
* MT=2 SIGMA = 2.83 +- 0.11 B *
* MT=102 SIGMA = 0.57 +- 0.04 B *
* MT=102 RESONANCE INTEGRAL = 0.47 +- 0.05 B *
* *
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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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58-CE-140 HEDL EVAL-APR74 R.E.SCHENTER AND F.SCHMITTROTH
DIST-NOV84 H.GRUPPELAAR, ECN, PETTEN
************* REVISED BY H.GRUPPELAAR, NOV,84 *******************
FILE INFORMATION (UPDATED NOV 84)
MF=2 MT=151 RESONANCE PARAMETERS FROM NEW BNL-COMP. (3)
MULTI-LEVEL FORMULA UPTO EH=20 KEV
MF=3 MT= 1 TOTAL CROSS SECTION CALCULATED USING MOLDAUER
POTENTIAL FROM REF. (4) FOR E .GT. EH.
MF=3 MT= 2 ELASTIC CROSS SECTION FROM SIGT-SIGCAP-SIGIN FOR
E .GT. EH.
MF=3 MT= 4,51,52,.,.,91 INELASTIC CROSS SECTIONS CALCULATED
USING COMNUC-3 REFS.(5,6).
MF=3 MT=102 NEUTRON CAPTURE EVALUATED USING METHODS (NCAP CODE)
IN REFS.(1,2) FOR E .GT. EH.
MF=3 MT=251 MUBAR CALCULATED USING MOLDAUER POTENTIAL REF.(4).
MF=3 MT=252 STI CALCULATED FROM MUBAR (MT=251)
MF=4 MT=2 ANGULAR DISTRIBUTION ASSUMED ISOTROPIC
MF=4 NON-ELASTIC A.D. ASSUMED ISOTROPIC
MF=5 MT= 91 EVAPORATION SPECTRUM(LF=9) PARAMETERS OBTAINED USING
NCAP CODE REF.(2).
REFERENCES
1. F SCHMITTROTH AND RE SCHENTER,HEDL TME 73-63(AUG 1973).
2. F SCHMITTROTH,HEDL TME 73-79(NOV 1973).
3. SF MUGHABGHAB ET AL., NEUTRON CROSS SECTIONS VOL.1A (1981)
4. PA MOLDAUER,NUC.PHYS.47(1963)65.
5. CL DUNFORD,AI-AEC-12931(JULY 1970).
6. CL DUNFORD(PRIVATE COMMUNICATION).
2200M/S CAPTURE CROSS SECTION,BARNS.
(FROM RESONANCE PARAMETERS) = 0.57 B
COMPUTED RESONANCE INTEGRAL = 0.34 B
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