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62-Sm-154 NEA RCOM-JUN82 H.GRUPPELAAR,E.MENAPACE
JEF/DOC-30 DIST-JAN09 20090105
----JEFF-311 MATERIAL 6255
-----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=9813). *
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* 8-JAN-85: RESONANCE PARAM. CHANGED TO ORIGINAL SINGLE-LEVEL.
* 23-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
* 21-NOV-89: RESONANCE PARAMETERS OF NEGATIVE AND FIRST POSITIVE
* RESONANCE ADJUSTED BY ECN IN ORDER TO OBTAIN A
* BETTER AGREEMENT OF CALCULATED AND EXPERIMENTAL
* VALUES OF THERMAL CROSS SECTIONS AND RESONANCE
* INTEGRAL.
* 1-NOV-90: ADDITIONAL COMMENTS INSERTED
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* *
* MODIFICATIONS FOR JEF-2 62-SM-154 *
* *
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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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* *
* RESOLVED RESONANCE PARAMETERS WERE REPLACED BY DATA FROM *
* MOST RECENT BROOKHAVEN COMPILATION(MU84). *
* *
* RESONANCE PARAMETERS OF NEGATIVE AND FIRST POSITIVE *
* RESONANCE ADJUSTED BY ECN IN ORDER TO OBTAIN A BETTER *
* AGREEMENT OF CALCULATED AND EXPERIMENTAL VALUES OF *
* THERMAL CROSS SECTIONS AND RESONANCE INTEGRAL. *
* *
* EL=10-5 EV, EH=3.1036 KEV. *
* *
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* THERMAL VALUES (2200M/S): *
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* *
* CALCULATED VALUES: *
* MT=2 SIGMA = 11.0000 B *
* MT=102 SIGMA = 8.40000 B *
* MT=102 RESONANCE INTEGRAL = 33.7516 B *
* *
* EXPERIMENTAL VALUES: *
* MT=2 SIGMA = 11. +- 3. B *
* MT=102 SIGMA = 8.4 +- 0.5 B *
* MT=102 RESONANCE INTEGRAL = 32 +- 6 B *
* *
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* REFERENCES: *
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* *
* MU84: MUGHABGHAB,S.F. *
* NEUTRON CROSS SECTIONS VOLUME 1 *
* NEUTRON RESONANCE PARAMETERS AND THERMAL CROSS *
* SECTIONS, PART B, Z=61-100, ACADEMIC PRESS 1984 *
* *
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HEDL EVAL-APR74 R.E.SCHENTER AND F.SCHMITTROTH
DIST-JUL80 800730
FILE INFORMATION
MF=2 MT=151 RESONANCE PARAMETERS FROM NEW BNL-325 REF.(3).
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. A 1/V COMPONENT WAS ADDED TO
GIVE THE 2200 M/S CROSS SECTION OF REF.(3) FOR E .LT. EH
THE CALCULATED RESONANCE INTEGRAL AGREES(TO WITHIN
1 SIGMA) WITH THE VALUE GIVEN IN REF.(7).
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 AND DI GARBER,BNL 325,3ED,V1(JUNE 1973).
4. PA MOLDAUER,NUC.PHYS.47(1963)65.
5. CL DUNFORD,AI-AEC-12931(JULY 1970).
6. CL DUNFORD(PRIVATE COMMUNICATION).
7. AL POPE AND JS STORY, AEEW-M 1234(1973).
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