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AbstractAbstract
[en] The PWG 2 Task Group on Thermal Hydraulic System Behavior has discussed the subject of the use of best-estimate codes in the licensing process (codes that model thermal hydraulic processes are important to assessing safety system performance). The Task Group set out to determine the prevailing practices in member countries, concerning safety assessment and safety review of transients affecting the reactor coolant system. A summary of information provided by member countries in response to eleven questions is given: Who is Responsible for Safety Analysis? Who is Responsible for Review and Evaluation of Safety Analysis? Do the Regulations Permit the use of Best-Estimate Codes? What are the Requirements for What Constitutes a Best Estimate Code? What are the Requirements Concerning Code Documentation? What are the Requirements for Review of Code Models and Correlations? What are the Requirements Concerning Code Assessment? What are the Requirements Concerning Initial and Boundary Conditions? What are the Requirements Concerning Operability of Active Equipment? What are the Requirements Concerning Operator Actions?
Primary Subject
Source
Oct 1996; 24 p; OCDE-GD--1997-7
Record Type
Report
Report Number
Country of publication
ACCIDENT MANAGEMENT, COMPUTER CODES, LOSS OF COOLANT, MELTDOWN, NEA, PWR TYPE REACTORS, REACTOR ACCIDENT SIMULATION, REACTOR OPERATION, REACTOR OPERATORS, REACTOR SAFETY, RISK ASSESSMENT, SAFETY ANALYSIS, SAFETY ENGINEERING, SAFETY MARGINS, SAFETY REPORTS, SYSTEM FAILURE ANALYSIS, THERMAL HYDRAULICS
ACCIDENTS, ENGINEERING, ENRICHED URANIUM REACTORS, FLUID MECHANICS, HYDRAULICS, INTERNATIONAL ORGANIZATIONS, MANAGEMENT, MECHANICS, OECD, OPERATION, PERSONNEL, POWER REACTORS, REACTOR ACCIDENTS, REACTORS, SAFETY, SIMULATION, SYSTEMS ANALYSIS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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