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...

The direct measurement of plutonium in spent reactor fuel is an unmet challenge in international safeguards. In this simulation study, we investigate the use of the delayed gamma rays from fission product nuclei to determine the amount of fissile isotopes (Pu-239, Pu-241, and U-235) in irradiated light water reactor fuel assemblies. Fission is stimulated with an interrogating neutron source, an...

The fusion-fission hybrid system has the potential attractiveness of good safety performances and plenty of fuel compared to the fission reactor system and also easing the requirement of fusion plasma technology. It is a practical path to the early fusion application for energy production. In this paper, a fusion-driven subcritical reactor for energy multiplier, named FDS-EM, is proposed. It ca...

Introduction Safe operation of a nuclear reactor depends to a large extent on the behaviour of different fission products generated within the fuel. While most of the fission products settle down as dissolved state in the fuel matrix or as separate phases, the gaseous products, xenon(Xe), and krypton(Kr), and the volatile products, iodine(I), tellurium(Te), cesium(Cs), and rubidium(Rb), underg...

The Vienna TRIGA Mark II reactor was modelled by means of the Serpent-2 Monte Carlo burnup calculation code. The purpose of the modelling is the determination of core critical parameters and of nuclear fuel composition time evolution. This paper presents the Serpent-2 reactor model validation process carried out during the last year. Taking into account the irradiation history, the fuel composi...

The only significant development of the AUS system has been an extension.of the available cross-sections. That portion of the ENDF/B V data files which is unrestricted has been acquired from the IAEA Nuclear Data Section and the data processed for the AUS.ENDF2006 group library as required. In particular, a large set of fission product data has been processtid, sufficient for calculations of bo...

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...

Six advanced reactor concepts have been selected for Generation-IV reactors and are being investigated worldwide to meet the challenging goals of effective resource utilization and waste minimization (sustainability), improved safety, enhanced proliferation resistance, and reduced system cost. [1] The six systems are very high temperature reactor (VHTR), sodium-cooled fast reactor (SFR), superc...

Almost all major nuclear operations produce residues containing radioactive materials; in reactor operations, for example, the fission products, new elements (such as plutonium) produced by neutron irradiation and the unfissioned nuclear fuel are all radioactive. Some of this material can be put to further use: useful radioisotopes, for instance, can be extracted from the fission products and p...