Jaea's VHTR for Hydrogen and Electricity Cogeneration : Gthtr300c

Kunitomi, Kazuhiko; Yan, Xing; Nishihara, Tetsuo; Sakaba, Nariaki; Mouri, Tomoaki

doi:10.5516/net.2007.39.1.009

Cited by 78 publications

(41 citation statements)

References 4 publications

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“…By developing the balance of plant technologies, JAEA has completed a 10-year design study of commercial series GTHTR300C (Gas Turbine High Temperature Reactor of 300 MWe for Cogeneration), whose plant overview is depicted in Figure 1. Since the design has been reported elsewhere [17,18], only the latest results on the plant operational design are described in detail. Referring to Figure 2, GTHTR300C consists of a 600 MWt HTGR with outlet coolant temperature of 9508C, an intermediate heat exchanger (IHX) to supply 9008C process heat to thermal production plant for hydrogen or other industrial product, a direct-cycle recuperated gas turbine to generate power while circulating reactor coolant.…”

Section: Plant Design Descriptionmentioning

confidence: 99%

“…Table 1 gives the GTHTR300C base heat and power cogeneration rates, which may be reset according to site-specific load requirement as described in Section 2. In the base cogeneration, the reactor outlet coolant of [17]. The balance of the reactor thermal power is converted to electric power in the reactor gas turbine plant.…”

Section: Load-follow Performance Evaluationmentioning

confidence: 99%

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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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Section: Plant Design Descriptionmentioning

confidence: 99%

Section: Load-follow Performance Evaluationmentioning

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

Self Cite

View full text Add to dashboard Cite

show abstract

“…• Japan: The Japan Atomic Energy Agency (JAEA) continues development work begun under the former Japan Atomic Energy Research Institute (JAERI) on the Gas Turbine High Temperature Reactor 300 for Cogeneration (GTHTR300C) [19,20], which will scale up the technology from the JAEA 30 MW-thermal High Temperature Test Reactor (HTTR) [21] into a 600 MW-thermal configuration that shares design features with both the GA GT-MHR and the Areva Modular HTR except for being coupled to a horizontal turbine-generator for electricity production; however, deployment of the GTHTR300C is not envisioned until after 2030.…”

Section: Description Of the Prismatic Vhtrmentioning

confidence: 99%

Very High-Temperature Reactor (VHTR) Proliferation Resistance and Physical Protection (PR&PP)

Moses¹

2011

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“…It is planned that a vertical helically-coiled gas-gas heat exchanger like the IHX is adopted in the GTHTR300C. 10) Fig. 9 Historical trend of the primary coolant and secondary helium gas temperature at the IHX Fig.…”

Section: Development Of Design For Future Htgr 'Gthtr300c'mentioning

confidence: 99%

Thermal Performance of Intermediate Heat Exchanger during High-Temperature Continuous Operation in HTTR

Tochio

Nakagawa

2011

J. Nucl. Sci. Technol.

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To use the High-Temperature Gas-cooled Reactor (HTGR) system as a commercial reactor similar to the future HTGR 'GTHTR300C,' supplying stable high-temperature heat from the reactor to the heat utilization system such as the hydrogen production system over a prolonged period should be demonstrated. The 50-day high-temperature continuous operation with full power, which is the first long-term operation with a reactor outlet coolant temperature over 900 C, was achieved in March 2010 in the High Temperature Engineering Test Reactor (HTTR) of the Japan Atomic Energy Agency (JAEA). In order to supply stable high-temperature heat from the reactor to the heat utilization system using the HTTR, the heat exchange performance and structure integrity of the intermediate heat exchanger (IHX) should be confirmed. In this paper, the heat exchange performance and structure temperature of the IHX were evaluated with the high-temperature continuous operation data and compared with the designed one or estimated one. As a result, it was confirmed that the IHX can exchange stable high-temperature heat from the primary coolant to the secondary helium, and the IHX structure temperature is under the allowable working temperature in the operation. Moreover, it was confirmed that the heat exchange performance is almost the same as the designed one and that the structure temperature estimated with the analysis code is almost the same as the measured one.

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Jaea's VHTR for Hydrogen and Electricity Cogeneration : Gthtr300c

Cited by 78 publications

References 4 publications

Evaluation of high temperature gas reactor for demanding cogeneration load follow

Evaluation of high temperature gas reactor for demanding cogeneration load follow

Very High-Temperature Reactor (VHTR) Proliferation Resistance and Physical Protection (PR&PP)

Thermal Performance of Intermediate Heat Exchanger during High-Temperature Continuous Operation in HTTR

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