The core conversion studies of the Ghana Research Reactor Core started in 2006 and with the objective of designing an LEU core with similar operational capabilities as the original HEU core and with acceptable safety margins under both normal and accident conditions. Steadystate studies for converting the Ghana MNSR facility from HEU to LEU core have been performed using the PLTEMP/ANL V4.1 cod...

EPM’s Systems and Safety Analysis Division has worked tirelessly for decades to aid the continued safety and reliability of the American and International nuclear fleet. As the group continues to support the aging of these plants from the original Nuclear Renaissance, other projects have begun to support the certification of new reactor designs. Two projects currently undertaken by the EPM SSA ...

This summary deals with a fundamental question in any reactor model validation practice: given a body of available experiments, and an envisaged domain of reactor operating conditions (referred to as reactor application), can one develop a quantitative measure that measures the portion of the prior uncertainties of the reactor application that is covered by the available experiments? Coverage h...

The current overall safety criterion for both radioisotope and reactor power sources is containment or immobilization in the case of a reentry accident. In addition, reactors are to be designed to remain subcritical under conditions of land impact or water immersion. A very extensive safety test and analysis program was completed on the radioisotope thermoelectric generators (RTGs) in use on th...

Abstract Operating conditions in the liquid metal fast reactor, like higher power density, temperature gradient, and burnup, are more severe to fuel rod comparing light water reactor. The integrity safety of is very essential reactor safety. In this study, designed for M 2 LFR-1000, which a typical pool type lead cooled evaluated using performance analysis code named KMC-Fueltra. Irradiation be...

JOSHUA is a computational system developed to perform the extensive engineering and physics calculations needed in the design and analysis of Savannah River Plant (SRP) nuclear reactors. Application of this system significantly enhanced the efficiency, effectiveness, accuracy, and safety of nuclear reactor design and analysis. The unique features of SRP reactors, which necessitated the Site’s d...

Thermal stratification phenomena are very common in pool type reactor systems, such as the liquid-salt cooled Advanced High Temperature Reactor (AHTR) and liquid-metal cooled fast reactor systems. It is important to accurately predict the temperature and density distributions both for design optimization and accident analysis. Current reactor system analysis codes only provide lumped-volume bas...