10. REFERENCES
- Ishigami, T. et. al.:
User's Manual of ART Code for Analyzing FP Transport Behaviour During Core Meltdown Accident.
JAERI-M 88-093 (1988) (in Japanese)
- Kajimoto, M., et. al.:
The Validation of the ART Code Through Comparison with NSPP Experiments in the Steam-Air Atmosphere.
NEA/CEC/CEA CSNI Workshop on Aerosol Behaviour and Thermal Hydraulics in Containment, Fontenay-aux-Roses, 145 (1990)
- Kajimoto, M., et. al.:
Development of THALES-2, A Computer Code for Coupled Thermal- Hydraulics and FP Transport Analyses for Severe Accident at LWRs and Its Application to Analysis of FP Revaporization Phenomena.
Proceedings of the International Topical Meeting on Safety of Thermal Reactors, Portland, pp. 584-592 (1991)
- Hidaka, A. et. al.:
Experimental Analysis with ART Code on FP Behaviour Under Severe Accident Conditions.
Proceedings of Validation of Systems Transient Analysis Codes, FED, Volume 223, pp. 99-106, ASME (1995)
- Hidaka, A., et. al.:
Comparative Study of FP Deposition in WIND Project Piping by ART and VICTORIA.
Proceedings of the International Conference on Probabilistic Safety Assessment Methodology and Applications, Korea (PSA '95), pp. 241-246 (1995)
- Hidaka, A., et. al.:
Experimental Analysis of Aerosol Behaviors in Primary Piping With ART Code During Severe Accident.
Proceedings of the International Conference for Heat and Mass Transfer, pp. 577-587 (1996)
- Hidaka, A. et. al.:
Experimental Analyses of Iodine Behavior Under Severe Accident Conditions with ART.
Journal of Nuclear Materials, Volume 248, pp. 226-232 (1997)
NEA-1581/01, included references:
- Kajimoto, M., Hidaka, A., Muramatsu, K. and Sugimoto, J.:
ART Mod 2: A Computer Code for the Analysis of Radionuclide Transport and
Deposition under Severe Accident Conditions - Model Description and
User's Manual (Draft)
Department of Reactor Safety Research, Tokai Research Establishment, JAERI