Activation analysis of concrete and graphite in the experimental reactor RUS

Radiation Protection Dosimetry

Volumn 115, Issue 1-4, 2005, Pages 104-109

  Cometto, M ^a   Ridikas, D ^a   Aubert, M C ^a   Damoy, F ^a   Ancius, D ^a  

^a CEA SACLAY   (France)

Author keywords

[No Author keywords available]

Indexed keywords

CONCRETE; GRAPHITE;

ACCURACY; ARTICLE; CALCULATION; CHEMICAL ANALYSIS; CHEMICAL COMPOSITION; FRANCE; GEOLOGY; LIBRARY; MATERIALS HANDLING; METHODOLOGY; NEUTRON ACTIVATION ANALYSIS; NUCLEAR REACTOR; NUCLEAR WASTE; PLANNING; PREDICTION; RADIATION SHIELD; RELIABILITY; THEORETICAL MODEL; UNIVERSITY; VALIDATION PROCESS;

ALGORITHMS; COMPUTER SIMULATION; CONSTRUCTION MATERIALS; EQUIPMENT FAILURE; EQUIPMENT FAILURE ANALYSIS; FACILITY DESIGN AND CONSTRUCTION; FRANCE; GRAPHITE; MATERIALS TESTING; MODELS, STATISTICAL; MONTE CARLO METHOD; NEUTRONS; NUCLEAR REACTORS; RADIATION DOSAGE; RADIATION MONITORING; RADIATION PROTECTION; RADIOISOTOPES; RESEARCH; RISK ASSESSMENT;

EID: 27144434831     PISSN: 01448420     EISSN: None     Source Type: Journal    
DOI: 10.1093/rpd/nci049     Document Type: Article

References (3)

1. Briesmeister, J. F. for Group X-6 MCNP-A. A General Monte Carlo Code for Neutron and Photon Transport, Version 4A. LANL Report LA-12625-M (Los Alamos National Laboratory, Los Alamos, NM) (1993).
2. Wilson, W. B., England, T. R. and Van Riper, K. A. Status of CINDER '90 Codes and Data, Preprint Report (Los Alamos National Laboratory, Los Alamos, NM) LA-UR-99-361 (1999).
3. Cometto, M., Ancius, D. and Ridikas, D. Testing different data libraries in activation analysis of concrete and graphite from nuclear installations. In: Proceedings of the International Workshop on Nuclear Data for the Transmutation of Nuclear Waste, GSI-Darmstadt, Germany, 1-5 September (2003). Available on http://www-wnt.gsi.de/TRAMU.