Analysis of the PROFIL and PROFIL-2 sample irradiation experiments in Phénix for JEFF-3.1 nuclear data validation

Nuclear Science and Engineering

Volumn 160, Issue 2, 2008, Pages 232-241

  Tommasi, J ^a   Noguere G ^a  

^a IRFM   (France)

Author keywords

[No Author keywords available]

Indexed keywords

ACTINIDES; FAST REACTORS; FISSION PRODUCTS;

CAPTURE CROSS SECTIONS; DEGREE OF ACCURACY; EXPERIMENTAL TECHNIQUES; IRRADIATION EXPERIMENTS; ISOTOPIC ANALYSIS; NEODYMIUM ISOTOPES; NEUTRON SPECTRA; SIMILAR ANALYSIS;

ISOTOPES;

EID: 54149089470     PISSN: 00295639     EISSN: None     Source Type: Journal    
DOI: 10.13182/NSE160-232     Document Type: Article

References (11)

1. J. TOMMASI, E. DUPONT, and P. MARIMBEAU, "Analysis of Sample Irradiation Experiments in Phénix for JEFF-3.0 Nuclear Data Validation," Nucl. Sci. Eng., 154, 119 (2006).
2. J. M. RUGGIERI et al., "ERANOS-2.1: The International Code System for GEN-IV Fast Reactor Analysis," Proc. Int. Congress Advances in Nuclear Power Plants (ICAPP '06), Reno, Nevada, June 4-8, 2006, American Nuclear Society (2006).
3. "The JEFF-3.1 Nuclear Data Library," JEFF Report 21, Nuclear Energy Agency Data Bank, Organisation for Economic Co-operation and Development (2006).
4. J. TOMMASI et al., "Present Status of JEFF-3.1 Validation for Fast Reactors Using the ERANOS-2.1 Code System," Proc. Topi. Mtg. Reactor Physics (PHYSOR-2006), Vancouver, British Columbia, Canada, September 10-14, 2006, American Nuclear Society (2006).
5. 241Am Isotope: Summary," JEF-DOC 1086, Organisation for Economic Co-operation and Development/Nuclear Energy Agency (May 2005);
6. available to JEFF/EFF members on the Internet at http://www.nea.fr/html/ dbdata/projects/ jeffdoc.html;
7. see also, D. BERNARD, O. BOULAND, and A. SANTAMARINA, "Americium-241 Low Energy Cross-Section and Capture Isomeric Ratio Revision for JEFF3.1x," J. Nucl. Sci. Technol. (submitted for publication).
8. "Experimental Nuclear Reaction Data Library EXFOR," Nuclear Data Services, International Atomic Energy Agency (2006).
9. 240Pu Cross Sections in the Unresolved Resonance Energy Range-Special Care on the Sub-Threshold Fission Cross-Section," Proc. Int. Conf. New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing (PHYSOR 2002), Seoul, Korea, October 7-10, 2002, American Nuclear Society (2002).
10. M. B. CHADWICK et al., "ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology," Nucl. Data Sheets, 107,2931 (2006); see p. 2964.
11. G. GAILLARD-GROLEAS, F. SUDREAU, and D. WARIN, "Phénix Irradiation Program on Fuels and Targets for Transmutation," Proc. GLOBAL 2003, New Orleans, Louisiana, November 16-20, 2003, American Nuclear Society (2003).