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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Latest News
NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
C. M. Walter, P. G. Shewmon, J. P. Bacca
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 38-44
Technical Paper | Fuel | doi.org/10.13182/NT71-A30900
Articles are hosted by Taylor and Francis Online.
A metallic fuel-element modeling code (BEMOD) has been developed to describe the irradiation behavior of EBR-II driver fuels. BEMOD has been applied to both the present Mark LA and the advanced Mark II driver fuels. Good agreement on cladding diameter changes as a function of burnup is obtained between calculations and measurements on irradiated fuel elements. At a reactor power of 50 MW(th), the code calculations indicate that the Mark IA element is capable of about 3.5 at.% before a cladding ΔD/D of 2% is expected, while the Mark II design should be capable of about twice that burnup before a similar cladding ΔD/D is attained. The increase in reactor power to 62.5 MW(th) appears to have no appreciable effect on the above values.
