Publication

A Simplified Numerical Benchmark For Pool-Type Sodium Fast Reactors

Andreas Pautz, Konstantin Mikityuk, Carlo Fiorina, Stefan Radman
2018
Conference Papers

Abstract

The current work presents a simplified benchmark for a pool-type Sodium Fast Reactor based on a 2D (r-z) geometry for testing tightly-coupled spatial neutron transport, thermal-hydraulics and thermal-mechanics modeling. The new benchmark is motivated by development of the multi-physics OpenFOAM-based GeN-Foam code at the Laboratory for Reactor Physics and Systems Behaviour at the EPFL, Switzerland, and the FAST code system by the Advanced Nuclear Systems group at the Paul Scherrer Institut, Switzerland. Aiming at the improvement of modeling and code-to-code comparison, the benchmark could prove useful for developers of tightly-coupled multi-physics simulation tools for reactor analysis. The benchmark specification and the solutions obtained with GeN-Foam are presented and discussed in the paper.

Official source

https://infoscience.epfl.ch/entities/publication/dfc4b36a-d24b-4204-88ef-985cba6a32f2

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Andreas Pautz, Konstantin Mikityuk, Carlo Fiorina, Stefan Radman
2018
Conference Papers

Abstract

Official source

https://infoscience.epfl.ch/entities/publication/dfc4b36a-d24b-4204-88ef-985cba6a32f2

About this result

Ontological neighbourhood

Energy engineering

Nuclear power: Topics in nuclear power

Related concepts (19)

Nuclear reactor

A nuclear reactor is a device used to initiate and control a fission nuclear chain reaction or nuclear fusion reactions. Nuclear reactors are used at nuclear power plants for electricity generation and in nuclear marine propulsion. Heat from nuclear fission is passed to a working fluid (water or gas), which in turn runs through steam turbines. These either drive a ship's propellers or turn electrical generators' shafts. Nuclear generated steam in principle can be used for industrial process heat or for district heating.

Fast-neutron reactor

A fast-neutron reactor (FNR) or fast-spectrum reactor or simply a fast reactor is a category of nuclear reactor in which the fission chain reaction is sustained by fast neutrons (carrying energies above 1 MeV or greater, on average), as opposed to slow thermal neutrons used in thermal-neutron reactors. Such a fast reactor needs no neutron moderator, but requires fuel that is relatively rich in fissile material when compared to that required for a thermal-neutron reactor.

Integral fast reactor

The integral fast reactor (IFR, originally advanced liquid-metal reactor) is a design for a nuclear reactor using fast neutrons and no neutron moderator (a "fast" reactor). IFR would breed more fuel and is distinguished by a nuclear fuel cycle that uses reprocessing via electrorefining at the reactor site. The U.S. Department of Energy began designing an IFR in 1984 and built a prototype, the Experimental Breeder Reactor II. On April 3, 1986, two tests demonstrated the safety of the IFR concept.

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