ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Apr 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Industry Update—May 2025
Here is a recap of industry happenings from the recent past:
TerraPower’s Natrium reactor advances on several fronts
TerraPower has continued making aggressive progress in several areas for its under-construction Natrium Reactor Demonstration Project since the beginning of the year. Natrium is an advanced 345-MWe reactor that has liquid sodium as a coolant, improved fuel utilization, enhanced safety features, and an integrated energy storage system, allowing for a brief power output boost to 500-MWe if needed for grid resiliency. The company broke ground for its first Natrium plant in 2024 near a retiring coal plant in Kemmerer, Wyo.
Masao Yamamoto, Ken-Ichi Matsumoto
Nuclear Technology | Volume 89 | Number 2 | February 1990 | Pages 194-202
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT90-A34346
Articles are hosted by Taylor and Francis Online.
The development of spent-fuel reprocessing technology as well as mixed-oxide (MOX)fuel conversion and fabrication is indispensable to the establishment of the fast breeder reactor (FBR) fuel cycle. Ninety-two tons of MOX was fabricated in the Tokai Plutonium Fuel Fabrication Facility from 1966 until March 1988. The Tokai Plutonium Fuel Production Facility (PFPF) was completed in 1987. Since then, uranium and plutonium test runs for fuel fabrication have been continued at PFPF. Production of MOX fuel for the experimental Joyo FBR started in the second half of 1988, and for the prototype Monju FBR, production is scheduled to begin in 1989. A plutonium conversion facility with a capacity of 10 kg of MOX per day was finished in 1983 and coconversion is going well after cold and hot test operations. Continuous processing is also being tested to scale up the conversion throughput. The conceptual design of the FBR Fuel Recycling Pilot Plant was completed in 1986. A decision was made to construct a new hot test facility, the Recycling Equipment Test Facility. This facility will be equipped with plant-scale test components and equipment for testing irradiated FBR fuel and collecting hot data. In the Chemical Processing Facility, 11 experimental campaigns have been carried out using irradiated MOX fuel. Many cold tests in the Engineering Development Facilities have been continued. Recognizing the importance of international cooperation in developing FBR fuel recycling technology, Power Reactor and Nuclear Fuel Development Corporation actively exchanges information and carries out joint research with its counterparts in the United States, the United Kingdom, and the Federal Republic of Germany. Especially with the United States, collaboration was begun in 1988 in the areas of head-end process, extraction process, remote technology, and facility design.