JAEA has long been designing series of Gas Turbine High Temperature Reactor (GTHTR) based on advanced HTGR technologies developed through the construction and operation of the High Temperature Engineering Test Reactor (HTTR). Inherent safety characteristics of the GTHTR keep the reactor safe and stable condition with no risk of core meltdown even in the worst case accidents such as a primary pipe rupture, station blackout, etc. In addition to design studies of the GTHTR, JAEA conducted or will conduct several safety demonstration tests using the HTTR to examine the reactor transient behavior during the worst case accident and to validate and verify analytical tools of the design for an High Temperature Gas-cooled Reactor (HTGR). These tests are not only valuable to develop design tools, but also are effective to convince safety authority and average people that the GTHTR is a safe and reliable system to be acceptable after the Higashi-Nihon earthquake and to be deployed in 2020s. This paper describes safety design of the GTHTR and a safety demonstration test program of the HTTR. Also, it presents the results of safety evaluation during a primary pipe rupture and the following station blackout. The evaluation results revealed that the maximum fuel temperature is kept under the allowable limit and fission products are safety contained in the fuel due to salient safety characteristics.
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ASME 2011 Small Modular Reactors Symposium
September 28–30, 2011
Washington, DC, USA
Conference Sponsors:
- Standards and Certification
ISBN:
978-0-7918-5473-0
PROCEEDINGS PAPER
Safety Characteristics of GTHTR and Safety Demonstration Test Program Using HTTR
Kazuhiko Kunitomi,
Kazuhiko Kunitomi
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
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Xing Yan,
Xing Yan
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
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Hirofumi Ohashi
Hirofumi Ohashi
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
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Kazuhiko Kunitomi
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
Xing Yan
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
Hirofumi Ohashi
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
Paper No:
SMR2011-6611, pp. 375-380; 6 pages
Published Online:
February 21, 2012
Citation
Kunitomi, K, Yan, X, & Ohashi, H. "Safety Characteristics of GTHTR and Safety Demonstration Test Program Using HTTR." Proceedings of the ASME 2011 Small Modular Reactors Symposium. ASME 2011 Small Modular Reactors Symposium. Washington, DC, USA. September 28–30, 2011. pp. 375-380. ASME. https://doi.org/10.1115/SMR2011-6611
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