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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Senate committee hears from energy secretary nominee Chris Wright
Wright
Chris Wright, president-elect Trump’s pick to lead the U.S. Department of Energy, spent hours today fielding questions from members of the U.S. Senate’s committee on Energy and Natural Resources.
During the hearing, Wright—who’s spent most of his career in fossil fuels—made comments in support of nuclear energy and efforts to expand domestic generation in the near future. Asked what actions he would take as energy secretary to improve the development and deployment of SMRs, Wright said: “It’s a big challenge, and I’m new to government, so I can’t list off the five levers I can pull. But (I’ve been in discussions) about how to make it easier to research, to invest, to build things. The DOE has land at some of its facilities that can be helpful in this regard.”
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.
