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.
Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Lotfi A. Belblidia, Gerardo M. Grandi, Christian Jönsson
Nuclear Science and Engineering | Volume 148 | Number 2 | October 2004 | Pages 325-336
Technical Paper | doi.org/10.13182/NSE04-A2461
Articles are hosted by Taylor and Francis Online.
This paper discusses the model and results for the Peach Bottom 2 Turbine Trip Test 2 using Studsvik Scandpower's transient code SIMULATE-3K. All data pertaining to core, vessel, and scenario were taken from the NEA/OECD BWR benchmark specifications. Nuclear data were generated with Studsvik Scandpower's lattice code CASMO-4 and core analysis code SIMULATE-3. Comparisons to measured data, sensitivity to model options and data, as well as results from more limiting scenarios are presented. SIMULATE-3K captures well the pressure wave propagation, void collapse during the pressurization phase, and resulting power excursion.
