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Nuclear research reactor
 
The CROCUS research reactor of the École polytechnique fédérale de Lausanne, in Switzerland

Research reactors are nuclear fission-based nuclear reactors that serve primarily as a neutron source. They are also called non-power reactors, in contrast to power reactors that are used for electricity production, heat generation, or maritime propulsion.

Purpose

The neutrons produced by a research reactor are used for neutron scattering, non-destructive testing, analysis and testing of materials, production of radioisotopes, research and public outreach and education. Research reactors that produce radioisotopes for medical or industrial use are sometimes called isotope reactors. Reactors that are optimised for beamline experiments nowadays compete with spallation sources.

Technical aspects

Research reactors are simpler than power reactors and operate at lower temperatures. They need far less fuel, and far less fission products build up as the fuel is used. On the other hand, their fuel requires more highly enriched uranium, typically up to 20% U-235,[1] although some use 93% U-235; while 20% enrichment is not generally considered usable in nuclear weapons, 93% is commonly referred to as "weapons-grade". They also have a very high power density in the core, which requires special design features. Like power reactors, the core needs cooling, typically natural or forced convection with water, and a moderator is required to slow the neutron velocities and enhance fission. As neutron production is their main function, most research reactors benefit from reflectors to reduce neutron loss from the core.

Conversion to low enriched uranium

The International Atomic Energy Agency and the U.S. Department of Energy initiated a program in 1978 to develop the means to convert research reactors from using highly enriched uranium (HEU) to the use of low enriched uranium (LEU), in support of its nonproliferation policy.[2][3] By that time, the U.S. had supplied research reactors and highly enriched uranium to 41 countries as part of its Atoms for Peace program. In 2004, the U.S. Department of Energy extended its Foreign Research Reactor Spent Nuclear Fuel Acceptance program until 2019.[4]

As of 2016, a National Academies of Sciences, Engineering, and Medicine report concluded converting all research reactors to LEU cannot be completed until 2035 at the earliest. In part this is because the development of reliable LEU fuel for high neutron flux research reactors, that does not fail through swelling, has been slower than expected.[5] As of 2020, 72 HEU research reactors remain.[6]

Designers and constructors

While in the 1950s, 1960s and 1970s there were a number of companies that specialized in the design and construction of research reactors, the activity of this market cooled down afterwards, and many companies withdrew.

The market has consolidated today into a few companies that concentrate the key projects on a worldwide basis.

The most recent international tender (1999) for a research reactor was that organized by the Australian Nuclear Science and Technology Organisation for the design, construction and commissioning of the Open-pool Australian lightwater reactor (OPAL). Four companies were prequalified: Atomic Energy of Canada Limited (AECL), INVAP, Siemens and Technicatom. The project was awarded to INVAP that built the reactor. In recent years, AECL withdrew from this market, and Siemens and Technicatom activities were merged into Areva.

Classes of research reactors

Research centers

A complete list can be found at the List of nuclear research reactors.

Research centers that operate a reactor:

Reactor Name Country City Institution Power Level Operation Date
BR2 Reactor Belgium Mol Belgian Nuclear Research Center SCK•CEN 100 MW
Budapest Research Reactor[7] Hungary Budapest Hungarian Academy of Sciences Centre for Energy Research 5 MW[7] 1959[7]
Budapest University of Technology Training Reactor[8] Hungary Budapest Budapest University of Technology and Economics 100 kW 1969
ILL High-Flux Reactor France Grenoble Institut Laue-Langevin 63 MW[9]
RA-6 Argentina Bariloche Balseiro Institute / Bariloche Atomic Centre 1 MW[10] 1982[10]
ZED-2 Canada Deep River, Ontario AECL's Chalk River Laboratories 200 W[11] 1960
McMaster Nuclear Reactor Canada Hamilton, Ontario McMaster University 5 MW 1959
National Research Universal reactor Canada Deep River, Ontario AECL's Chalk River Laboratories 135 MW 1957
Petten nuclear reactors Netherlands Petten Dutch Nuclear Research and consultancy Group,[12] EU Joint Research Centre 30 kW and 60MW 1960
ORPHEE France Saclay Laboratoire Léon Brillouin 14 MW 1980
FRM II Germany Garching Technical University of Munich 20 MW 2004
HOR Netherlands Delft Reactor Institute Delft, Delft University of Technology 2 MW
Mainz Germany Mainz Universität Mainz, Institut für Kernchemie 100 kW[13]
TRIGA Mark II[14] Austria Vienna Technical University Vienna, TU Wien, Atominstitut 250 kW 1962[14]
IRT-2000 Bulgaria Sofia Bulgarian Academy of Sciences research site 2 MW
OPAL Australia Lucas Heights, New South Wales Australian Nuclear Science and Technology Organisation 20 MW 2006
IEA-R1 Brazil São Paulo Instituto de Pesquisas Energéticas e Nucleares 3.5 MW 1957
IRT-2000[15] Russia Moscow Moscow Engineering Physics Institute 2.5 MW[15] 1967[15]
SAFARI-1 South Africa Pelindaba South African Nuclear Energy Corporation 20 MW[16] 1965[16]
High-Flux Advanced Neutron Application Reactor South Korea Daejeon Korea Atomic Energy Research Institute 30 MW[17] 1995[17]
LVR-15 Czech Republic Řež Nuclear Research Institute 10 MW[18] 1995[18]
North Carolina State University Reactor Program United States Raleigh, North Carolina North Carolina State University 1 MW[19] 1953[19]
High Flux Isotope Reactor United States Oak Ridge, Tennessee Oak Ridge National Laboratory
Advanced Test Reactor United States Idaho Idaho National Laboratory 250 MW[20]
University of Missouri Research Reactor United States Columbia, Missouri University of Missouri 10 MW 1966
Maryland University Training Reactor United States College Park, Maryland University of Maryland 250 kW[21] 1970[21]
Washington State University Reactor United States Pullman, Washington Washington State University 1 MW[22]
CROCUS Switzerland Lausanne École polytechnique fédérale de Lausanne
Maria reactor Poland Świerk-Otwock National Centre for Nuclear Research 30 MW 1974
TRIGA Mark I United States Irvine, California University of California, Irvine
ITU TRIGA Mark-II Training and Research Reactor Turkey Istanbul Istanbul Technical University
ETRR-1 Egypt Inshas Nuclear Research Center 2 MW 1961
ETRR-2 Egypt Inshas Nuclear Research Center 22 MW 1997
Ghana Research Reactor-1[23] Ghana Accra National Nuclear Research Institute of the Ghanan Atomic Energy Commission 30 kW

Decommissioned research reactors:

Reactor Name Country City Institution Power Level Operation Date Closure Date Decommissioned
ASTRA Austria Seibersdorf Austrian Institute of Technology 10 MW 1960 1999
BER II Germany Berlin Helmholtz-Zentrum Berlin 10 MW 1973 2019[24]
CONSORT United Kingdom Ascot, Berkshire Imperial College 100 kW
JASON reactor United Kingdom Greenwich Royal Naval College 10 kW 1962 1996
MOATA Australia Lucas Heights Australian Atomic Energy Commission 100 kW 1961 1995
High Flux Australian Reactor Australia Lucas Heights Australian Atomic Energy Commission 1958 2007
HTGR (Pin-in-Block Design) United Kingdom Winfrith, Dorset International Atomic Energy Agency 20MWt 1964 1976 July 2005[25]
DIDO United Kingdom Harwell, Oxfordshire Atomic Energy Research Establishment 1990
Nuclear Power Demonstration Canada Deep River, Ontario AECL's Rolphton plant 20 MW 1961 1987
NRX Canada Deep River, Ontario AECL's Chalk River Laboratories 1952 1992
PLUTO reactor United Kingdom Harwell, Oxfordshire Atomic Energy Research Establishment 26 MW 1957 1990
Pool Test Reactor Canada Deep River, Ontario AECL's Chalk River Laboratories 10 kW 1957 1990
WR-1 Canada Zdroj:https://en.wikipedia.org?pojem=Nuclear_research_reactor
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