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Accession number;06A0254194
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| Title;Improvement of Core Dynamics Analysis of Control Rod Withdrawal Test in HTGR |
| Author;
TAKAMATSU KUNIYOSHI
(Nihongenshiryokukenkyukaihatsukiko)
NAKAGAWA SHIGEAKI
(Nihongenshiryokukenkyukaihatsukiko)
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Journal Title;Transactions of the Atomic Energy Society of Japan
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Journal Code:L4596A
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ISSN:1347-2879
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VOL.5;NO.1;PAGE.45-56(2006)
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| Figure&Table&Reference;FIG.21, TBL.4, REF.15 |
| Pub. Country;Japan |
| Language;Japanese |
| Abstract;The HTTR (High Temperature Engineering Test Reactor), which has thermal output of 30 MW, coolant inlet temperature of 395.DEG.C. and coolant outlet temperature of 850.DEG.C./950.DEG.C. is the first high temperature gas-cooled reactor (HTGR) in Japan. HTGRs have high inherent safety potential to accident condition. Safety demonstration tests using the HTTR are underway in order to demonstrate such excellent inherent safety features of HTGRs. The reactivity insertion tests demonstrate rapid increase of reactor power by withdrawing the control rod without operating the reactor power control system. The experimental results show the negative reactivity feedback effect and the slow temperature transient. A one-point core dynamics approximation with one fuel channel had applied to our analysis. It was found that the analytical results couldn't simulate accurately the reactor power behavior. This report proposes an original new method with fuel channels and temperature coefficients in some regions of the core. It is crucial that the analytical results using this method can simulate experimental values and excellent inherent safety features of HTGRs under accident conditions. (author abst.) |
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