ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
Latest Magazine Issues
Aug 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
September 2026
Nuclear Technology
Fusion Science and Technology
August 2026
Latest News
Centrus, X-energy sign enrichment contract as TRISO-X expands TX-1 campus
Centrus Energy Corp. will be providing X-energy with enrichment services for low-enriched uranium and high-assay, low-enriched uranium to support X-energy’s planned deployments of Xe-100 small modular reactors and TRISO-X fuel, according to the terms of a new contract signed by the companies. The fuel will be produced at Centrus’s American Centrifuge Plant in Piketon, Ohio. In turn, X-energy will provide Centrus with prepayments to help support expanding the capacity of Centrus’s domestic commercial enrichment program.
Xing L. Yan, Tetsuaki Takeda, Tetsuo Nishihara, Kazutaka Ohashi, Kazuhiko Kunitomi, Nobumasa Tsuji
Nuclear Technology | Volume 163 | Number 3 | September 2008 | Pages 401-415
Technical Paper | Fission Reactors | doi.org/10.13182/NT08-A3998
Articles are hosted by Taylor and Francis Online.
A rupture of the primary piping in the helium-cooled and graphite-moderated high-temperature gas-cooled reactor (HTGR) represents a design-basis event that should not result in significant safety consequences. In such a loss-of-coolant event, the reactor would be shut down inherently, and the decay heat would be removed passively with the ultimate reactor temperature rise being less than the design limit. Still, an important concern for reactor safety continues to be graphite oxidation damage to the fuel and core should a major air ingress take place through the breached primary pressure boundary. Two major cases of air ingress are studied. The first case results from the rupture of a control rod or refuel access standpipe atop the reactor pressure vessel (RPV). To rule out the possibility of such a standpipe rupture, a design change is proposed in the vessel top structure. The feasibility of the modified vessel local structure is evaluated. The second case of air ingress results from the rupture of one or more main coolant pipes on the lower body of the RPV. Experiment and analysis are performed to understand the multiphased air ingress phenomena in the depressurized reactor. Accordingly, a new passive mechanism of sustained counter air diffusion is proposed and shown to be effective in preventing major air ingress through natural circulation in the reactor. The results of the present study are expected to enhance the HTGR safety and economics.