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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
SMR simulator development is focus of North Carolina grant
The North Carolina Collaboratory, a research funding agency established by the North Carolina General Assembly to partner with academic institutions and government entities, has awarded a grant to North Carolina State University and GE Hitachi Nuclear Energy (GEH) for research into small modular reactors. The funded research project, “Academic Boiling Water–Small Modular Reactor (BW-SMR) Simulator for Research, Development, and Educational Purposes,” focuses on the development of a digital-based simulator for GEH’s BWRX-300, a Gen III+ light water SMR.
Marco Pellegrini, Hiroaki Suzuki, Hideo Mizouchi, Masanori Naitoh
Nuclear Technology | Volume 186 | Number 2 | May 2014 | Pages 241-254
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-107
Articles are hosted by Taylor and Francis Online.
Because of the high-magnitude earthquake and consequent tsunami that struck the east coast of Japan on March 11, 2011, at 14:46, Tokyo Electric Power Company's Fukushima Daiichi nuclear power plant experienced station blackout (SBO) resulting in a nuclear accident unprecedented in time and extent. Simulation of such an accident by means of computer codes is largely dependent on the applied boundary conditions and physical models. However, still-unknown boundary conditions and unclear phenomena result in uncertain computed quantities. In this study, first, the boundary conditions of emergency systems are theoretically derived, starting from a discussion of the reactor available measured quantities and related uncertainties. Then, newly implemented physical models (e.g., wetwell condensation mechanism), which were not accounted for in historical studies of long-term SBOs, are explained. As an early method for accident clarification and explanation regarding effective boundary conditions, results from the SAMPSON severe accident code were compared with theoretical values. The results of SAMPSON compared with the measured quantities available have shown that despite successful safety operations performed by the plant operators in Fukushima Daiichi Unit 3, the eventual lack of batteries (for systems operation and measurement reading) led to plant conditions of low core water level at high pressure, nullifying the attempt of the subsequent alternative water injection to prevent core degradation.