A GFR benchmark: Comparison of transient analysis codes based on the ETDR concept

Problems about future energy availability, climate changes, and air quality seem to play an important role in energy production. While current reactor generations provide a guaranteed and economical energy production, new nuclear power plant generation would increase the ways and purposes in which nuclear energy can be used. To explore these new technological applications, several governments, industries, and research communities decided to contribute to the next reactor generation, called “Generation IV.” Among the six Gen-IV reactor designs, the Gas Cooled Fast Reactor (GCFR) uses a direct-cycle helium turbine for electricity generation and for a -free thermochemical production of hydrogen. Additionally, the use of a fast spectrum allows actinides transmutation, minimizing the production of long-lived radioactive waste in an integrated fuel cycle. This paper presents an analysis of GCFR fuel cycle optimization and of a thermal-hydraulic of a GCFR-prototype under steady-state and transient conditions. The fuel cycle optimization was performed to assess the capability of the GCFR to transmute MAs, while the thermal-hydraulic analysis was performed to investigate the reactor and the safety systems behavior during a LOFA. Preliminary results show that limited quantities of MA are not affecting significantly the thermal-fluid-dynamics behavior of a GCFR core.

Section: The Gas-cooled Fast Reactormentioning

confidence: 74%

Section: Etdr: Core Fuelled With Minor Actinidesmentioning

confidence: 99%

Section: Etdr: Core Fuelled With Minor Actinidesmentioning

confidence: 99%

See 1 more Smart Citation

GCFR Coupled Neutronic and Thermal‐Fluid‐Dynamics Analyses for a Core Containing Minor Actinides

Castelliti

Bomboni

Cerullo

et al. 2009

“…The objective is to allow decay heat extraction by passive methods during the first 24 hours following an accident. Studies into the natural convection behavior of Gen IV GFR concepts are presented for instance in [22,23].…”

Section: Generation IV and A New Start For Gcfr Developmentmentioning

confidence: 99%

Gas‐Cooled Fast Reactor: A Historical Overview and Future Outlook

Rooijen

2009

A review is given of developments in the area of Gas-Cooled Fast Reactors (GCFR) in the period from roughly 1960 until 1980. During that period, the GCFR concept was expected to increase the breeding gain, the thermal efficiency of a nuclear power plant, and alleviate some of the problems associated with liquid metal coolants. During this period, the GCFR concept was found to be more challenging than liquid-metal-cooled reactors, and none were ever constructed. In the second part of the paper, we provide an overview of the investigations on GCFR since the year 2000, when the Generation IV Initiative rekindled interest in this reactor type. The new GCFR concepts focus primarily on sustainable nuclear power, with very efficient resource use, minimum waste, and a very strong focus on (passive) safety. An overview is presented of the main design characteristics of these Gen IV GCFRs, and a literature list is provided to guide the interested reader towards more detailed publications.

“…The final demonstration elements will be representative of the GFR core and will feature ceramic hex-tubes, such that the core outlet temperature will be increased to 850 • C. The FP6 Euratom contribution to ALLEGRO has been on specific design and safety studies. In-depth studies have been performed in the following areas: With regard to the last point, a major programme of benchmarking of transient analysis codes was carried out by cross-comparing the simulations for reference scenarios obtained by different users and different computer codes, ahead of the application of the analysis of real plant transients [10]. This work will be extended in the 7th Framework Programme by comparing the results of these codes against specifically commissioned experimental studies.…”

Section: Allegro: a Gfrmentioning

confidence: 99%

Gas Cooled Fast Reactor Research and Development in the European Union

Stainsby

Peers

Mitchell

et al. 2009

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).