Analysis of LOFT experiment L6-8C-3 using the RELAP5 code
T.H. Chen, C.L. Nalezny, S.M. Modro
Abstract
T.H. Chen, C.L. Nalezny, S.M. Modro
Abstract
The Loss-of-Fluid Test (LOFT) facility, operated by EG and G Idaho, Inc., is a 55-MW(t) experimental reactor designed to simulate the major components and system response of a commercial pressurized water reactor (PWR) during hypothetical loss-of-coolant accidents. LOFT experiment L6-8C-3, conducted on August 31, 1982, simulated a small break in the primary coolant system, a transient that has a high probability of occurrence during the lifetime of a commercial PWR. The experiment was designed to investigate a small-break transient with extended operation of the reactor coolant pumps and to demonstrate the use of pump current (or power) monitoring as a diagnostic technique for accident management. Post-experiment calculations were performed with the RELAP5/MOD1 computer code using the specified initial conditions and the measured initial and boundary conditions. The objectives of the calculations were to evaluate the capability of the RELAP5/MOD1 code to calculate the thermal-hydraulic phenomena that occurred during the experiment.
A significance statement is not available in the OpenAlex record.
A contribution statement is not available in the OpenAlex record.
Method details are not available in the OpenAlex metadata.
Findings are not separately available in the OpenAlex metadata.
Limitations are not available in the OpenAlex metadata.
Application details are not available in the OpenAlex metadata.
The Loss-of-Fluid Test (LOFT) facility, operated by EG and G Idaho, Inc., is a 55-MW(t) experimental reactor designed to simulate the major components and system response of a commercial pressurized water reactor (PWR) during hypothetical loss-of-coolant accidents. LOFT experiment L6-8C-3, conducted on August 31, 1982, simulated a small break in the primary coolant system, a transient that has a high probability of occurrence during the lifetime of a commercial PWR. The experiment was designed to investigate a small-break transient with extended operation of the reactor coolant pumps and to demonstrate the use of pump current (or power) monitoring as a diagnostic technique for accident management. Post-experiment calculations were performed with the RELAP5/MOD1 computer code using the specified initial conditions and the measured initial and boundary conditions. The objectives of the calculations were to evaluate the capability of the RELAP5/MOD1 code to calculate the thermal-hydraulic phenomena that occurred during the experiment.
Key concepts: Nuclear engineering, Coolant, Transient (computer programming), Pressurized water reactor, Thermal hydraulics, Loss-of-coolant accident, Environmental science, Engineering