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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
WIPP’s SSCVS: A breath of fresh air
This spring, the Department of Energy’s Office of Environmental Management announced that it had achieved a major milestone by completing commissioning of the Safety Significant Confinement Ventilation System (SSCVS) facility—a new, state-of-the-art, large-scale ventilation system at the Waste Isolation Pilot Plant, the DOE’s geologic repository for defense-related transuranic (TRU) waste in New Mexico.
Hidemasa Kato, Tohru Haga, Shigeru Ohteru, Hiroshi Kamikawa
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 361-380
Technical Paper | doi.org/10.13182/NSE84-A18505
Articles are hosted by Taylor and Francis Online.
A core management analysis of a 165-MW(electric) plutonium-uranium mixed-oxide-fueled heavy water reactor, Fugen, has been carried out and compared with some of the operational data through the initial cycle and three reload cycles. During these burnup cycles, the Fugen reactor has experienced refueling of 72 plutonium-uranium fuel bundles and 76 UO2 fuel bundles, including four special bundles for irradiating test samples. The core burnup, thermal flux distribution, power distribution, coolant flow distribution, etc., were calculated and compared with measurements. The root-mean-square (rms) error of the calculated thermal flux over the three-dimensional spatial nodes was found to be ∼3% for various core conditions, and the rms error of the calculated core flow distribution was within 2%. The reload patterns have been chosen in such a way that mixed oxide and UO2 fuel bundles can exist in a mixed bed loading with no attendant reactor control problems.