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44-Ru-103 NEA EVAL-JUN06 NEA/WPEC Subgroup 23
DIST-JAN09 20090105
----JEFF-311 MATERIAL 4446
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
*************************** JEFF-3.1.1 *************************
** **
** Original data taken from: ENDFB-7 +New Eval **
** Modification: Int. FP Library NEA WPEC/SG23 **
******************************************************************
==============================================================
File produced by WPEC Subgroup 23 in 2004-2005
- WPEC: NEA Working Party on Evaluation Cooperation
- SG23: International Fission Product Library, IFPL
File obtained by merging: &&
- Resolved Resonances (MLBW) <350 eV : Ref.1 &&
- Unresolved Resonances 350 eV - 100 keV : CENDL 3 &&
- Fast neutron region >100 keV : CENDL 3 &&
&&
Calculated thermal cross sections & resonance integrals: &&
--------------------------------------------- &&
Reaction Cross section Res. integral &&
(barn) (barn) &&
Total 6.2043E+00 - &&
Elastic 5.0327E+00 - &&
Capture 1.1716E+00 4.70E+01 &&
--------------------------------------------- &&
Reference:
1) S.F.Mughabghab: Atlas of Neutron Resonances, to be
published by Elsevier, 2006 (5-th edition of BNL-325)
==============================================================
THIS EVALUATION WAS COMPLETED BY LIANG QICHANG, THE THEORETICAL
CALCULATION WAS DONE BY ZHANG ZHENGJUN FIRST,THEN RE-CALCULATED
BY GE ZHIGANG WITH THE CODE SUNF[1].
01-09 REVISION WAS MADE BY ZHENG-JUN ZHANG AND QING-BIAO SHEN
/CNDC/
MF = 1 GENERAL INFORMATION
MT=451 COMMENTS AND DICTIONARY
MF = 2 RESONANCE PARAMETERS
MT=151 RESOLVED AND UNRESOLVED RESONANCE PARAMETERS WERE TAKEN
FROM 44-RU-103 OF JENDL-3.
CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS)
2200 M/S RES. INTEG.
TOTAL 13.10+0 -
ELASTIC 5.100+0 -
CAPTURE 8.000+0 35.3124+0
MF = 3 NEUTRON CROSS SECTIONS
BELOW 100 KEV, RESONANCE PARAMETERS WERE GIVEN. ABOVE 100 KEV,
NO EXPERIMENTAL DATA WAS AVAILABLE FOR 44-RU-103, THE EVALUATION
WAS BASED ON THE THEORETICAL CALCULATION, THE CALCULATION WERE
MADE WITH THE THEORY CODE SUNF[1], THE CODE APMN[2] WAS USED TO
AUTOMATICALLY GET THE OPTIMAL PARAMETER OF OPTICAL POTENTIAL FOR
NEUTRON CHANNEL. THE DIRECT INELASTIC SCATTERING DATA WERE
CALCULATED BY THE CODE DWUCK4[3].
MT = 1 TOTAL CROSS SECTION
NO EXPERIMENTAL DATA WAS AVAILABLE FOR TOTAL CROSS SECTION.
THE THEORETICAL CALCULATION RESULT WERE DIRECTLY ADOPTED AS
THE RECOMMENDED DATA, IT WAS IN GOOD AGREEMENT WITH THE
EXPERIMENTAL DATA OF NATURAL RUTHENIUM[4-5].
MT = 2 ELASTIC SCATTERING CROSS SECTION
NO EXPERIMENTAL DATA WAS AVAILABLE FOR ELASTIC SCATTERING
CROSS SECTION. THE (TOTAL - NONELASTIC CROSS SECTIONS) WAS
CALCULATED AS THE ELASTIC CROSS SECTION.
MT = 3 NON-ELASTIC CROSS SECTION
NO EXPERIMENTAL DATA WAS AVAILABLE FOR NON-ELASTIC CROSS
SECTION, IT WAS OBTAINED BY THE SUM OF PARTIAL CROSS SECTIONS
MT = 4, 51 - 91 INELASTIC SCATTERING CROSS SECTIONS
MT = 16 (N,2N) CROSS SECTION
MT = 17 (N,3N) CROSS SECTION
MT = 22 (N,N'A) CROSS SECTION
MT = 28 (N,N'P) CROSS SECTION
MT = 102 CAPTURE CROSS SECTION
MT = 103 (N,P) CROSS SECTION
MT = 104 (N,D) CROSS SECTION
MT = 105 (N,T) CROSS SECTION
MT = 107 (N,A) CROSS SECTION
NO EXPERIMENTAL DATA WERE AVAILABLE FOR THESE CROSS SECTIONS,
THE THEORETICAL CALCULATION RESULTS WERE ADOPTED.
MF = 4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
CALCULATED WITH SUNF[1]
MF = 5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
CALCULATED WITH SUNF[1]
REFERENCES
[1] ZHANG JINGSHANG, COMMUN. OF NUCL. DATA PROG., 17, 18 (1997)
[2] SHEN QINGBIAO, 'A CODE APMN FOR AUTOMATICALLY SEARCHING
OPTIMAL OPTICAL POTENTIAL PARAMETERS BELOW 300 MEV',
, 25, 19 (2001)
[3] P.D. KUNZ, "DISTORTED WAVE CODE DWUCK4", UNIVERSITY OF COLO-
RADO
[4] D.G.FOSTER JR, J. PR/C, 3, 576(1971)
[5] M.DIVADEENAM, J. DA/B, 28, 3834(1968)
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