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Mathematics & Computation
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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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
The fire that powers the universe: Harnessing inertial fusion energy
It was a laser shot for the ages. By achieving fusion ignition on December 5, 2022, Lawrence Livermore National Laboratory proved that recreating the “fire” that fuels the sun and the stars inside a laboratory on Earth was indeed scientifically possible.
I Ming Huang, Yuh Ming Ferng, Shih Jen Wang
Nuclear Technology | Volume 160 | Number 3 | December 2007 | Pages 294-307
Technical Paper | Reactor Safety | doi.org/10.13182/NT07-A3900
Articles are hosted by Taylor and Francis Online.
The severe accident management guideline (SAMG) was developed and implemented at the Kuosheng nuclear power plant (NPP) in Taiwan at the end of 2003. The Kuosheng NPP is a Mark-III boiling water reactor (BWR)-6 located in the north of Taiwan. The SAMG of the Kuosheng NPP is developed based on the BWR Owners Group Emergency Procedure and Severe Accident Guidelines. In this paper, MELCOR 1.8.5 is used to investigate the effectiveness of the Kuosheng SAMG and to analyze the reactor coolant system (RCS) bleed-and-feed strategy in a postulated station blackout (SBO) accident since this accident is a dominant sequence that can induce core damage. These simulation results can be applied for the typical BWR-6 NPPs. Based on the simulation results, the major events of an SBO accident without any operator actions, including core uncovery, cladding oxidation, hydrogen generation, fuel relocation, vessel failure, and containment failure, are well presented. The RCS bleed-and-feed strategy can cool down the hot core and bring the vessel into the stable condition in the SBO accident with high-pressure core spray injection according to the Kuosheng SAMG. The reactor pressure vessel depressurization before the reactor liquid level reaches one-fourth of the core liquid level can prevent damage to the core fuel. However, the water temperature of the suppression pool will reach saturation temperature, and the containment pressure may challenge the containment integrity. These phenomena were not considered while developing the SAMG.