Fuel and Fission Gas Behavior during Rise-to-Power Test of the High Temperature Engineering Test Reactor(HTTR)
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概要
- 論文の詳細を見る
The rise-to-power tests of the High Temperature Engineering Test Reactor (HTTR) have been carried out successfully by the Japan Atomic Energy Research Institute (JAERI). For the safe operation of HTTR, the continuous and reliable measurement of the coolant activity is required to evaluate the fuel performance during normal operating conditions. In order to measure the primary coolant radioactivity (PCR), the PCR instrumentation of the safety protection system, the fuel failure detection (FFD) system and the primary coolant sampling system have been installed in the primary circuit. The PCR was less than 103 MBq/m3, and measured Kr and Xe isotopes were less than 0.1 MBq/m3 during the rise-to-power tests. The measured fractional releases are constant at 2×10−9 up to 60% of the reactor power, and then increase to 7×10−9 at full power operation. The prediction shows good agreement with the measured value. These results showed that the release mechanism varied from recoil to diffusion of the generated fission gas from the contaminated uranium in the fuel compact matrix.
- 社団法人 日本原子力学会の論文
- 2003-09-25
著者
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Sumita Junya
Oarai Establishment Japan Atomic Energy Research Institute
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Sawa Kazuhiro
Office Of Planning Japan Atomic Energy Research Institute
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UETA Shohei
Oarai Establishment, Japan Atomic Energy Research Institute
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EMORI Koichi
Oarai Establishment, Japan Atomic Energy Research Institute
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TAKAHASHI Masashi
Nuclear Fuel Industries, Ltd.
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Ueta Shohei
Oarai Establishment Japan Atomic Energy Research Institute
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Emori Koichi
Oarai Establishment Japan Atomic Energy Research Institute
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Takahashi Masashi
Nuclear Fuel Industries Ltd.
関連論文
- Fuel and Fission Gas Behavior during Rise-to-Power Test of the High Temperature Engineering Test Reactor(HTTR)
- Effect of Heat Treatment on TEM Microstructures of Zirconium Carbide Coating Layer in Fuel Particle for Advanced High Temperature Gas Cooled Reactor