Development and testing of a revised ENDF/B-VII capture cross section for 113Cd

International Conference on the Physics of Reactors 2008, PHYSOR 08

Volumn 1, Issue , 2008, Pages 260-265

  Mosteller, Russell D ^a   MacFarlane, Robert E ^a   Mughabghab, Said F ^b   Kim, Soon Sam ^c,d  

^a LOS ALAMOS NATIONAL LABORATORY   (United States)

^b BROOKHAVEN NATIONAL LABORATORY   (United States)

^c IDAHO NATIONAL LABORATORY   (United States)

^d LAWRENCE LIVERMORE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

CADMIUM; URANIUM COMPOUNDS;

CAPTURE CROSS SECTIONS; DEVELOPMENT AND TESTING; ENDF/B-VII.0; HIGHLY ENRICHED URANIUM; MEASURED VALUES; NITRATE SOLUTIONS; NUCLEAR DATA LIBRARY; SCATTERING WIDTH;

DETERIORATION;

EID: 79953846113     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (12)

1. Chadwick, M. B., et al., 2006. ENDF/B-VII.0: Next generation evaluated nuclear data library for nuclear science and technology, Nuclear Data Sheets, 107, 2931-3059.
2. Firestone, R., 2004. Lawrence Berkeley National Laboratory, private communication (2004).
3. Kim, S.S., 2006a. Analysis of high enriched uranyl nitrate solution containing cadmium, Proceedings of PHYSOR 2006, Advances in Nuclear Analysis and Simulation, Vancouver, Canada.
4. Kim, S.S., 2006b. Highly enriched uranyl nitrate solution containing cadmium, HEU-SOL-THERM-049, International Handbook of Evaluated Criticality Safety Benchmark Experiments, EA/NSC/DOC(95)03, OECD Nuclear Energy Agency.
5. Lloyd, C.L., Clayton, E.D., Wilson, R.E., McBroom, R.C., Jones, R.R., 1987. Critical experiments using high-enriched uranyl nitrate with cadmiumabsorber, Nucl. Technol., 79, 82-91.
6. rd Ed., Brookhaven National Laboratory.
7. McCabe, J., Smith, A.B., Meadows, J.W., 1993. Evaluated nuclear data Files for the naturally occurring isotopes of cadmium, ANL/DM-129, Argonne National Laboratory.
8. McLane, V., Ed., 2001. ENDF-102 data formats and procedures for the evaluated nuclear data file ENDF-6, BNL-NCS-44945, Brookhaven National Laboratory.
9. Meadows, J.W., Whaling, J.F., 1961. Thermal neutron absorption cross Sections by the pulsed source Method, Nucl. Sci. Eng., 9, 132-136.
10. Mughabghab, S.F., 2006. Atlas of Neutron Resonances, Elsevier (Holland).
11. Widder, F., Brunner, J., 1968. Total cross section of cadmium for neutrons of energy between 0.01 and 20 eV, Nukleonik, 11, 297-298.
12. X-5 Monte Carlo Team, 2003. MCNP - A general monte carlo n-particle transport code, version 5,volume I: overview and theory, LA-UR-03-1987, Los Alamos National Laboratory.