The source of all liquid, gaseous and solid radioactive waste in the pressure water reactor (PWR) nuclear power plant (NPP) originate from leakage of fission products out of the fuel rods into the primary coolant and neutron activation of materials within and around the primary coolant system and reactor vessel. The source term design used to determine the concentrations of radionuclides in the...

The effect of variation in thermal conductivity of light water reactor fuel elements on core response during loss-of-coolant accident scenarios is examined. Initially, a simplified numerical analysis is utilized to determine the time scales associated with dissipation of stored energy from the fuel into the coolant once the fission reaction is stopped. The analysis is then followed by full reac...

This document summarizes the large program of chemical research and development which led to selection of fuel and coolant compositions for the Molten-Salt Reactor Experiment (MSRE) and for subsequent reactors of this type. Chemical behavior of the LiF-BeFrZrFrUF4 fuel mixture and behavior of fission products during power operation of MSRE are presented. A discussion of the chemical reactions w...

Transmutation of burnup products for a typical VVER-1000 reactor in fusion-fission hybrid has been investigated using MCNPX 2.6.0 calculation code. Burnup fission was performed 1000 MW practical power VVER core UO2 fuel and light water as its coolant moderator, well. The have classified separated according to their half-lives usages, the remaining wastes were used fuels reactor. also implemente...

INTRODUCTION In pebble bed reactors (PBRs), fuel pebbles containing TRISO particles continuously circulate within the core during operation, while the coolant fluid, either helium gas (in Pebble Bed Gas-cooled Reactors) or molten flibe salt (in Pebble Bed-Advanced High Temperature Reactors), continuously passes through the pebbles to transfer the heat generated by fission reactions out of the c...

The aim of this study is to examine a magnetohydrodynamic (MHD) power generation system for the space applications using a nuclear fission reactor as the heat source. This MHD system uses He/Xe mixed gas as coolant instead of alkali-metal-seeded inert gas. The interrelation between the specific heat of the coolant and the mass flow rate was examined. When the specific heat decreases due to incr...

As part of the reactor dynamics activities of FZK/IRS, the qualification of a detailed 3D CFD model of a reactor pressure vessel is a key step in safety evaluations for improving predictive capabilities and acceptability of commercial CFD tools in reactor physics. The VVER-1000 Coolant Transient Benchmark, initiated by OECD, represents an excellent opportunity for validation. In this work a CFD...

HYPER (HYbrid Power Extraction Reactor) is the accelerator-driven transmutation system developed by KAERI (Korea Atomic Energy Research Institute). HYPER is designed to transmute long-lived transuranic actinides and fission products such as Tc and I. HYPER adopts a fast neutron system and Pb-Bi is used as core coolant and target material. Pb-Bi corrosion is one of the main factors considered to...