Fast Reactor Research Research Articles

Fast reactor thermal hydraulics in the Dutch PIONEER program

The multi-year research program carried out by NRG and funded by the Dutch ministry of economic affairs and climate is called ‘Program for Innovation and cOmpetence development for NuclEar infrastructurE and Research’ (PIONEER). The program comprises seven themes, i.e. long term operation, nuclear modelling and simulation, nuclear safety and compliance, fuels & materials, radioactive waste management, radiation protection, and innovative nuclear systems. One of the pillars in the theme of innovative nuclear systems is fast reactor research, particularly in the field of thermal hydraulics. This paper provides an overview of all fast reactor thermal hydraulics activities in the program, covering development and validation of System Thermal Hydraulics (STH) and 3D (engineering as well as high-fidelity) Computational Fluid Dynamics (CFD) codes and simulation approaches. Applications range from fundamental turbulent heat transport to core, pool and system thermal hydraulics. With the recent improvements in computational infrastructure and power, also further developments of multi-scale and multi-physics computational approaches are being integrated in the PIONEER program. A generic coupling tool ‘myMuscle’ is under development which is introduced in this paper. Recent results and current developments are presented together with an outlook for the results to be expected at the end of the current multi-year program and beyond.

SARAX: A new code for fast reactor analysis part I: Methods

Abstract A renaissance in fast reactor research and development and the rapid development of computing technologies have encouraged improvements in fast reactor modeling and calculation. A new code named SARAX has been developed. This paper reviewed current fast reactor neutronics analysis codes and provided an overview of SARAX developments. We introduced the following three methods: a hybrid method for cross-section generation, a two-level coarse mesh method for transport calculation acceleration, and a combined sensitivity and uncertainty analysis method. We discussed preliminary tests to show the benefits of these methods from two perspectives: (1) replacing the flux solver from neutron diffusion to neutron transport and (2) using a hybrid method rather than using the all Monte Carlo method to generate the cross-sections. We discussed an error cancelation phenomenon based on the numerical benchmarks.

铅冷快堆研究概述

铅冷快堆研究概述

Gas cooled fast reactor research in Europe

Research on the gas-cooled fast reactor system is directed towards fulfilling the ambitious long term goals of Generation IV (Gen IV), i.e., to develop a safe, sustainable, reliable, proliferation-resistant and economic nuclear energy system. In common with other fast reactors, gas-cooled fast reactors (GFRs) have exceptional potential as sustainable energy sources, for both the utilisation of fissile material and minimisation of nuclear waste through transmutation of minor actinides. The primary goal of GFR research is to develop the system primarily to be a reliable and economic electricity generator, with good safety and sustainability characteristics. However, for the longer term, GFR retains the potential for hydrogen production and other process heat applications facilitated through a high core outlet temperature which, in this case, is not limited by the characteristics of the coolant. In this respect, GFR can inherit the non-electricity applications of the thermal HTRs in a sustainable manner in a future in which natural uranium becomes scarce. GFR research within Europe is performed directly by those states who have signed the “System Arrangement” document within the Generation IV International Forum (the GIF), specifically France and Switzerland and Euratom. Importantly, Euratom provides a route by which researchers in other European states, and other non-European affiliates, can contribute to the work of the GIF, even when these states are not signatories to the GFR System Arrangement in their own right. This paper is written from the perspective of Euratom's involvement in research on the GFR system, starting with the 5th Framework Programme (FP5) GCFR project in 2000, through the FP6 project between 2005 and 2009 and looking ahead to the proposed activities within the current 7th Framework Programme (FP7). The evolution of the GFR concept from the 1960s onwards is discussed briefly, followed by the current perceived role, objectives and progress with the Generation IV GFR system.

Fast Reactor Development in the United States

This article chronicles the rise and fall of fast-reactor research in the United States. Research on fast reactors began at the end of World War II and represented a large fraction of the total U.S. research effort on civilian nuclear energy until the early 1980s. The goal of most of this research was to develop a plutonium breeder reactor capable of producing more plutonium from U-238 than is consumed. But with the termination of the Clinch River Breeder Reactor project in 1983, fast reactor development in the United States essentially ended. Safety issues played a role in this end to the fast breeder reactor program, but more important reasons were nuclear proliferation concerns and a growing conviction that breeder reactors would not be needed or economically competitive with light water reactors for decades, if ever.

Gas Cooled Fast Reactor Research and Development in the European Union

Gas‐cooled fast reactor (GFR) research is directed towards fulfilling the ambitious goals of Generation IV (Gen IV), that is, to develop a safe, sustainable, reliable, proliferation‐resistant and economic nuclear energy system. The research is directed towards developing the GFR as an economic electricity generator, with good safety and sustainability characteristics. Fast reactors maximise the usefulness of uranium resources by breeding plutonium and can contribute to minimising both the quantity and radiotoxicity nuclear waste by actinide transmutation in a closed fuel cycle. Transmutation is particularly effective in the GFR core owing to its inherently hard neutron spectrum. Further, GFR is suitable for hydrogen production and process heat applications through its high core outlet temperature. As such GFR can inherit the non‐electricity applications that will be developed for thermal high temperature reactors in a sustainable manner. The Euratom organisation provides a route by which researchers in all European states, and other non‐European affiliates, can contribute to the Gen IV GFR system. This paper summarises the achievements of Euratom′s research into the GFR system, starting with the 5th Framework programme (FP5) GCFR project in 2000, through FP6 (2005 to 2009) and looking ahead to the proposed activities within the 7th Framework Programme (FP7).