A research program is outlined to theoretically and experimentally establish the effectiveness and acceptability of on-line sequestering of fission product gases (FPGs) as they are generated in a fissile fuel pin using adsorbents and/or molecular sieves selectively distributed within the lower spring-plenum region of the LWR fuel. If successful this innovation can be implemented in existing and next generation LWRs and may: • reduce accident source term (releasable FPGs); • enhance reactor safety and acceptance; • extend fuel life suppressing clad swelling and fuel failure; • reduce thermal neutron poisons in high flux core regions; • improve operational and economical performance; • require only minor changes to fuel pin assembly and use; • use in LWRs with no license or tech-specifications impact.
Skip Nav Destination
18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4933-0
PROCEEDINGS PAPER
On-Line Sequestration of Fission Product Gases in Operating Nuclear Reactors Available to Purchase
Gary M. Sandquist,
Gary M. Sandquist
Applied Science Professionals, LLC, Salt Lake City, UT
Search for other works by this author on:
Jay F. Kunze
Jay F. Kunze
Idaho State University, Pocatello, ID
Search for other works by this author on:
Gary M. Sandquist
Applied Science Professionals, LLC, Salt Lake City, UT
Jay F. Kunze
Idaho State University, Pocatello, ID
Paper No:
ICONE18-29326, pp. 457-462; 6 pages
Published Online:
April 8, 2011
Citation
Sandquist, GM, & Kunze, JF. "On-Line Sequestration of Fission Product Gases in Operating Nuclear Reactors." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 5. Xi’an, China. May 17–21, 2010. pp. 457-462. ASME. https://doi.org/10.1115/ICONE18-29326
Download citation file:
8
Views
Related Proceedings Papers
Related Articles
Nuclear Fission, Today and Tomorrow: From Renaissance to Technological Breakthrough (Generation IV)
J. Pressure Vessel Technol (August,2011)
Facts & Fission
Mechanical Engineering (December,2009)
Estimation of Tritium and Dust Source Term in European DEMOnstration Fusion Reactor During Accident Scenarios
ASME J of Nuclear Rad Sci (July,2019)
Related Chapters
Nuclear Reactor Safety Systems
Nuclear Reactor Thermal-Hydraulics: Past, Present and Future
Studies Performed
Closed-Cycle Gas Turbines: Operating Experience and Future Potential
Introduction
Fundamentals of Nuclear Fuel