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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
Framatome begins expansion of facilities in Virginia
An official groundbreaking last week at Framatome’s Mill Ridge Road facility, in Lynchburg, Va., marks the start of a $50 million expansion and an eventual addition of 500 employees, according to the nuclear company.
Wei-Nian Su, Shih-Jen Wang, I-Ming Huang, Show-Chyuan Chiang
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 253-264
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3760
Articles are hosted by Taylor and Francis Online.
Containment flooding is an important strategy for severe accident management of a conventional boiling water reactor (BWR) system. The execution of containment flooding requires information about the water level in the primary containment. However, there is no instrument to measure the drywell water level for most Mark-III systems. Furthermore, because of the design feature of the Mark-III containment, the water level in the containment does not necessarily guarantee that there is an equivalent water level in the drywell. Therefore, the development of a drywell water level computational aid becomes very useful. The purpose of this work is to develop and validate the drywell water level computational aid and to investigate the implementation of the proposed computational aid on the containment flooding strategy of a Mark-III system. The Kuosheng nuclear power plant (NPP) is a typical BWR-6 NPP with Mark-III containment, and the Severe Accident Management Guideline (SAMG) of the Kuosheng NPP has been developed based on the BWR Owners' Group Emergency Procedure Guidelines and Severe Accident Guidelines, Revision 2. Therefore, the Kuosheng NPP is selected as the plant for study, and the MAAP4 code is chosen as the tool for analysis.