High-Temperature Continuous Operation of the HTTR

Takamatsu, Kuniyoshi; Sawa, Kôichiro; Kunitomi, Kazuhiko; Hino, Ryutaro; Ogawa, Masuro; Komori, Yoshihiro; Nakazawa, T.; Iyoku, Tatsuo; Fujimoto, Nozomu; Nishihara, Tetsuo; Shinozaki, Masayuki

doi:10.3327/taesj.j11.020

Cited by 11 publications

(5 citation statements)

References 3 publications

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“…Salient characteristics of HTGRs including not only the reliable supply of the high-temperature heat but also inherent safety features have been confirmed through several service operations and safety demonstration tests of the HTTR [2,3]. As a recent status of the HTTR, the continuous high-temperature operation with reactor outlet coolant temperature at 950 • C for 50 days has been performed successfully in 2010 [4].…”

Section: Introductionmentioning

confidence: 83%

Fuel performance under continuous high-temperature operation of the HTTR

Ueta

Aihara

Sakaba

et al. 2014

Journal of Nuclear Science and Technology

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The HTTR (high-temperature engineering test reactor) fuel, the first mass-produced HTGR (hightemperature gas-cooled reactor) fuel in Japan, has been fabricated with high quality on the basis of design principle and safety criteria to minimize both as-fabricated failure and on-operating-additional failure of the coated fuel particle. A precise technology for evaluating irradiation performance of the HTTR fuel has been developed by measuring fission gas released from the fuel and constructing the fission gas release model. Through the HTTR operations, including the continuous high-temperature operation at 950 • C for 50 days, the measured fractional release of fission gas from the fuel was less than 1.2 × 10 −8 , and a superior irradiation performance of Japanese HTGR fuel has been demonstrated. The HTTR fuel technologies could make a prospect for realization of the VHTR (very high temperature reactor) as a Generation IV nuclear power plant as well as the practical HTGR for the first time. This paper describes the fuel performance under continuous high-temperature operation of the HTTR.

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Section: Introductionmentioning

confidence: 83%

Fuel performance under continuous high-temperature operation of the HTTR

Ueta

Aihara

Sakaba

et al. 2014

Journal of Nuclear Science and Technology

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“…The selection of the 850 °C turbine inlet in the baseline was made in 2001 based on then available technologies. JAEA's high‐temperature engineering test reactor (HTTR) has since demonstrated long‐term operation at 950 °C with no deviation of fuel and equipment performance behavior from the 850 °C reactor operation . Furthermore, the recent material advances made on commercial gas turbine and aircraft engines support 950 °C metal temperature for turbine blades .…”

Section: Design Descriptionmentioning

confidence: 99%

Evaluation of GTHTR300A nuclear power plant design with dry cooling

Yan

Satō

Inaba

et al. 2014

Int. J. Energy Res.

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SUMMARY GTHTR300A is a power plant design based on high‐temperature gas‐cooled reactor. It relies on exclusive dry cooling for production and in emergency, a practice not found in existing and other proposed plants. Besides well‐known environmental benefits, successful use of dry cooling may provide the new found safety advantage because it avoids water‐related event such as tsunami or generation of explosive hydrogen. In the GTHTR300A, the reactor coolant is used to drive a direct‐cycle gas turbine, and further dry systems are provided to meet the three general cooling requirements. The system to reject power generation waste heat couples the reactor and a natural draft air cooling tower by a closed helium circulation loop. Careful design and operational measures are introduced to ensure the viability of economics, which proves difficult in existing plants. Separately, a natural convective air system is used to remove core decay heat in emergency. Detailed simulation shows that the system placed outside the reactor can maintain the temperatures of reactor fuel and structure below design limits even in case of simultaneous loss of coolant and station blackout. Finally, the study shows that the spent fuel may be stored in dry wells and safely cooled by natural convective air. By reliance on economic and safe dry cooling, the design succeeds in making inland construction feasible even without source of cooling water, and the resulting benefit to safety and environment is compelling in light of the 2011 Fukushima accident due to tsunami. Copyright © 2014 John Wiley & Sons, Ltd.

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“…JAEA has developed a 30 MWt and 9508C high temperature test reactor (HTTR), whose operation began in 1998 and continues successfully to date [14][15][16]. With the experience, nuclear structural materials including IG-110 core graphite and Hastalloy-XR heat-resistant steel and significant know-how including design codes and licensing methods are qualified to 122 X.L.…”

Section: Plant Design Descriptionmentioning

confidence: 99%

Evaluation of high temperature gas reactor for demanding cogeneration load follow

Yan¹,

Satō²,

Tachibana³

et al. 2012

Journal of Nuclear Science and Technology

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Modular nuclear reactor systems are being developed around the world for new missions among which is cogeneration for industries and remote areas. Like existing fossil energy counterpart in these markets, a nuclear plant would need to demonstrate the feasibility of load follow including (1) the reliability to generate power and heat simultaneously and alone and (2) the flexibility to vary cogeneration rates concurrent to demand changes. This article reports the results of JAEA's evaluation on the high temperature gas reactor (HTGR) to perform these duties. The evaluation results in a plant design based on the materials and design codes developed with JAEA's operating test reactor and from additional equipment validation programs. The 600 MWt-HTGR plant generates electricity efficiently by gas turbine and 9008C heat by a topping heater. The heater couples via a heat transport loop to industrial facility that consumes the high temperature heat to yield heat product such as hydrogen fuel, steel, or chemical. Original control methods are proposed to automate transition between the load duties. Equipment challenges are addressed for severe operation conditions. Performance limits of cogeneration load following are quantified from the plant system simulation to a range of bounding events including a loss of either load and a rapid peaking of electricity.

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High-Temperature Continuous Operation of the HTTR

Cited by 11 publications

References 3 publications

Fuel performance under continuous high-temperature operation of the HTTR

Fuel performance under continuous high-temperature operation of the HTTR

Evaluation of GTHTR300A nuclear power plant design with dry cooling

Evaluation of high temperature gas reactor for demanding cogeneration load follow

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