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44-Ru-102 NEA RCOM-JUL82 H.GRUPPELAAR,E.MENAPACE
JEF/DOC-30 DIST-JAN09 20090105
----JEFF-311 MATERIAL 4443
-----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=9331). *
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* 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 44-RU-102 *
* *
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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. *
* *
* EL=10-5 EV, EH=1.610 KEV. *
* *
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* THERMAL VALUES (2200M/S): *
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* *
* CALCULATED VALUES: *
* MT=2 SIGMA = 3.94928 B *
* MT=102 SIGMA = 1.29991 B *
* MT=102 RESONANCE INTEGRAL = 3.21470 B *
* *
* EXPERIMENTAL VALUES: *
* MT=2 SIGMA = NOT AVAILABLE *
* MT=102 SIGMA = 1.21 +- 0.07 B *
* MT=102 RESONANCE INTEGRAL = 4.2 +- 0.1 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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COMPILATION
-----------
THE COMPILATION AT THE NEA DATA BANK WAS BASED ON ENDF/B-V
DATA MAKING THE FOLLOWING MODIFICATIONS.
1) THE UPPER LIMIT OF THE RESONANCE RANGE IS NOT CONSISTENT WITH
CROSS SECTION DATA. IT WAS CHANGED FROM 1.6116 KEV TO 1.61 KEV.
2) THE ELASTIC SCATTERING CROSS SECTION AT 1.61 KEV FOR THE
HIGHER ENERGY RANGE IS NOT GIVEN IN ENDF/B-V. IT WAS ESTIMATED
AS 7.6 BARNS BY EYE-GUIDE.
3) THE CAPTURE CROSS SECTION FOR THE LOWER ENERGY RAGE IS NOT
GIVEN AT 1.61 KEV IN ENDF/B-V. IT WAS ESTIMATED AS 5.11 MILLI-
BARNS FROM ITS 1/V SHAPE.
4) THE TOTAL AND INELASTIC SCATTERING CROSS SECTIONS WERE
RE-CALCULATED FROM PARTIAL CROSS SECTIONS.
5) THE TRANSFORMATION MATRIX OF THE ANGULAR DISTRIBUTION OF
ELASTICALLY SCATTERED NEUTRONS WAS INSERTED BY CRECTJ5.
HEDL,RCN EVAL-FEB80 R.E.SCHENTER AND F.SCHMITTROTH
DIST-JUL80 800729
HEDL EVAL-FEB80 R.E.SCHENTER AND F.SCHMITTROTH
HEDL EVAL-FEB80 F.M.MANN, D.L.JOHNSON, G.NEELY
RCN EVAL-FEB80 H.GRUPPELAAR
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
ENERGY REGION ABOVE RESONANCE REGION UPDATED BY
COMBINING AVAILABLE INTEGRAL AND DIFFERENTIAL DATA
USING THE GENERALIZED LEAST SQUARES ADJUSTMENT CODE
FERRET (HEDL-TME 77-51)
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 CALCULATED FROM MOLDAUER
POTENTIAL
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).
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