Integral Test Facilities and Thermal-Hydraulic System Codes in Nuclear Safety Analysis

Passive system Evaluation by using integral thermal-hydraulic test facility in passive NPP(nuclear power plant) PSA(probabilistic safety assessment) process

Passive safety engineered systems are designed to take effect by physical phenomena or passive procedure during the scenario of imaginary accident of AP600/AP1000/CAP1400 passive safety type nuclear power plant. Generally, associative thermal-hydraulic experiments have been studied to support specific physical phenomenon research or evaluation model development in these scenarios. Data from T-H...

Thermal–hydraulic analysis of the coil test facility for CFETR

BACKGROUND Performance test of the China Fusion Engineering Test Reactor (CFETR) central solenoid (CS) and toroidal field (TF) insert coils is of great importance to evaluate the CFETR magnet performance in relevant operation conditions. The superconducting magnet of the coil test facility for CFETR is being designed with the aim of providing a background magnetic field to test the CFETR CS ins...

Integral Behavior of the Atlas Facility for a 3-inch Small Break Loss of Coolant Accident

Over the past 30 years, several large integral facilities have been utilized in order to understand transient behavior in nuclear power plants. The main objective of these integral facilities was to enhance our physical understanding of transient phenomena during LOCA or non-LOCA transients. An integral database was also used as a basis for the development and verification of thermal hydraulic ...

Nuclear Power Thermal and Hydraulic Power Electric Power Distribution

Issues Associated with Industry-developed Thermal-hydraulic Codes

SUBJECT: ISSUES ASSOCIATED WITH INDUSTRY-DEVELOPED THERMAL-HYDRAULIC CODES We are responding to the Staff Requirements Memorandum dated November 7, 2000 [Reference 1], in which the Commission requested the ACRS to provide a more detailed discussion on how the perceived weaknesses with industry-developed thermal-hydraulic codes may adversely affect the NRC's regulatory role and to provide more s...