44-Ru-104 NEA RCOM-JUL82 H.GRUPPELAAR,E.MENAPACE
JEF/DOC-30 DIST-JAN09 20090105
----JEFF-311 MATERIAL 4449
-----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=9333). *
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* 1-AUG-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
* 1-NOV-90: ADDITIONAL COMMENTS INSERTED
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* *
* MODIFICATIONS FOR JEF-2 44-RU-104 *
* *
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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(MU81). *
* *
* EL=10-5 EV, EH=1.511 KEV. *
* *
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* THERMAL VALUES (2200M/S): *
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* *
* CALCULATED VALUES: *
* MT=2 SIGMA = 8.08481 B *
* MT=102 SIGMA = 0.297187 B *
* MT=102 RESONANCE INTEGRAL = 5.79917 B *
* *
* EXPERIMENTAL VALUES: *
* MT=2 SIGMA = NOT AVAILABLE *
* MT=102 SIGMA = 0.32 +- 0.02 B *
* MT=102 RESONANCE INTEGRAL = 4.3 +- 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
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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=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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