Nuclear research reactors do not generate electricity. Instead, they produce neutrons primarily for research, radioisotope production, and nuclear education and training. Since 1942, about 884 research reactors have been built in 71 countries. As of 2023, 227 reactors were operational in 54 countries, while 520 had been decommissioned or were undergoing decommissioning.1
The world’s first research reactor, “Chicago Pile 1,” achieved the first sustained nuclear chain reaction. Built in 1942 under the stands of the University of Chicago’s football stadium, it played a pivotal role in the Manhattan Project during World War II.
Countries with research reactors (71) significantly outnumber those with commercial nuclear power plants (32). For instance, Malaysia, Libya, Peru, and Nigeria operate research reactors but do not have nuclear power plants. These countries rely on imports of enriched fuel and nuclear technology from nations with established nuclear industries, such as the United States, Russia, and China.
The construction of new research reactors has slowed in recent decades. Many countries have determined that existing reactor capacity is sufficient to meet their scientific and industrial needs. International collaboration often allows countries to share access to operational reactors. Additionally, new reactors are expensive to build and face complex regulatory approval processes. These factors, among others, have reduced demand for new research reactors.
The neutrons generated in nuclear research reactors are used to bombard specific materials, producing radioisotopes with broad applications in medicine. For example: Technetium-99m (Tc-99m) is widely used in diagnostic imaging such as bone scans and cardiac stress tests. Iodine-131 is used to treat thyroid disorders, and Cobalt-60 is used in radiotherapy for treating cancer.2
Radioisotopes also play a critical role in industrial applications. Gamma rays emitted by Iridium-192 and Cobalt-60 are used in non-destructive testing to detect cracks, voids, or defects in welds, pipelines, and metal structures. Krypton-85 and Strontium-90 are employed to monitor the thickness of materials like paper, plastics, and metals.3
The fuel cycle of research reactors is like that of nuclear power reactors. These reactors use enriched uranium, and their fuel cycle includes fuel fabrication, utilization in the reactor, and the subsequent temporary storage, reprocessing, or direct disposal of spent nuclear fuel.4
In the early years of research reactor operation, waste management was not a priority. Spent fuel, including high-enriched uranium (HEU), was often stored on-site, posing significant security and non-proliferation risks. This challenge is particularly acute for countries with research reactors but no or limited nuclear power programs, as they often lack the infrastructure and resources to manage spent fuel effectively.5
A partial solution has been to return spent fuel to the country of origin. Key initiatives include the Russian Research Reactor Fuel Return (RRRFR) Program, launched in 1999 for fuel supplied by Russia, and the U.S. Foreign Research Reactor Spent Nuclear Fuel (FRR SNF) Acceptance Program, established in 1996 for fuel originating in the United States.
1 International Atomic Energy Agency, Research Reactor Database, accessed November 16, 2024, https://nucleus.iaea.org/rrdb/#/home
2 Australian Nuclear Science and Technology Organisation, “What are radioisotopes,” accessed November 16, 2024, Link
3 Center for Nondestructive Evaluation, Iowa State University, “Nondestructive Evaluation Techniques,” accessed November 17, 2024, https://www.cnde.iastate.edu/
4 International Atomic Energy Agency, “Research reactor fuel cycle,” accessed November 17, 2024, https://www.iaea.org/topics/research-reactor-fuel-cycle
5 International Atomic Energy Agency, “Available Reprocessing and Recycling Services for Research Reactor Spent Nuclear Fuel,” IAEA Nuclear Energy Series, No. NW-T-1.11, 2017, Link
