Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 1
Description
More than 100 papers were presented. The meeting was divided in 56 sessions and covered the following topics: Plant Operation, Retrofitting and Maintenance Experience; Steam Generator Operation and Maintenance; Artificial Intelligence and Expert Systems; Seismic Technologies for Plant Design and Operations; Aging Management and Life Extension; Two-Phase Flow Modeling and Applications; Severe Accidents and Degraded Core Thermal Hydraulics; Plant Simulators, Analyzers, and Workstations; Advanced Nuclear Fuel Challenges; Recent Nuclear Power Station Decommissioning Experiences in the USA; Application of Probabilistic risk assessment/Probabilistic safety assessment (PRA/PSA) in Design and Modification; Numerical Modeling in Thermal Hydraulics; General Thermal Hydraulics; Severe Accident Management; Licensing and Regulatory Requirements; Advanced Light Water Reactor Designs to Support Reduced Emergency Planning; Best Estimate loss-of-coolant (LOCA) Methodologies; Plant Instrumentation and Control; LWR Fuel Designs for Improved Thermal Hydraulic Performance; Performance Assessment of Radioactive Waste Disposal; Thermal Hydraulics in Passive Reactor Systems; Advances in Man-Machine Interface Design and the Related Human Factors Engineering; Advances in Measurements and Instrumentation; Computer Aided Technology for non-destructive evaluation (NDE) and Plant Maintenance Plant Uprating; Flow-Accelerated Corrosion in Nuclear Power Plants; Advances in Radiological Measurement and Analysis Risk Management and Assessment; Stability in Thermal Hydraulic Systems; Critical heat flux (CHF) and Post Dryout Heat Transfer; Plant Transient and Accident Modeling
Availability note (English)
Available from INIS in electronic formFiles
35095456.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 772 p.
- Report number
- INIS-XA-N--080
Conference
- Title
- 4. international topical meeting on nuclear thermal hydraulics, operations and safety
- Dates
- 5-8 Apr 1994
- Place
- Taipei, Taiwan (China)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 35095456
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING; S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Is Lead record
- Yes
- Descriptors DEI
- BWR TYPE REACTORS; CRITICAL HEAT FLUX; EMERGENCY PLANS; FLOW MODELS; LEADING ABSTRACT; LOSS OF COOLANT; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR DECOMMISSIONING; REACTOR OPERATORS; REACTOR SAFETY; REACTOR SIMULATORS; RISK ASSESSMENT; STEAM GENERATORS; THERMAL HYDRAULICS; TWO-PHASE FLOW; WATER COOLED REACTORS
- Descriptors DEC
- ABSTRACTS; ACCIDENTS; ANALOG SYSTEMS; BOILERS; CALCULATION METHODS; DECOMMISSIONING; ENRICHED URANIUM REACTORS; FLUID FLOW; FLUID MECHANICS; FUNCTIONAL MODELS; HEAT FLUX; HYDRAULICS; MATHEMATICAL MODELS; MECHANICS; PERSONNEL; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SIMULATORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Refs, figs, tabs