Project of the GT-MHR high-temperature helium reactor with gas turbine

Kiryushin, A. I.; Kodochigov, N. G.; Kouzavkov, N.G.; Ponomarev-Stepnoi, N. N.; Gloushkov, E.S.; Grebennik, V.N.

doi:10.1016/s0029-5493(97)00099-x

Cited by 78 publications

(30 citation statements)

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“…The overall load-follow system of the GTHTR300C integrates four control strategies below: The first two strategies are known effective to control rapid transients such as loss of generator load in the HTGR direct-cycle gas turbine power generation systems [8,11,21,22]. They are expected to be also effective to control similar events in the present cogeneration system despite the additional topping IHX.…”

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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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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“…Conceptual design of the GT-MHR was done by GA [5] and further development is being carried out in Russia with support from the US government [6]. A PCU has two major parts, the turbomachine and the heat exchangers.…”

Section: Gt-mhr Power Conversion Unitmentioning

confidence: 99%

COMBINED ACTIVE/PASSIVE DECAY HEAT REMOVAL APPROACH FOR THE 24 MWt GAS-COOLED FAST REACTOR

Cheng¹,

Ludewig²

2007

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“…[3][4][5][6][7][8][9][10] Within this scenario the LWRs waste is reprocessed by uranium extraction (UREX) to build two different types of fuels, the Driver Fuel (DF), rich in fissile isotopes (mainly 239 Pu and 241 Pu) and the Transmutation Fuel (TF), rich in capturing nuclides ( 238 Pu, 240 Pu, 242 Pu and 241 Am). Table 1 reports the initial composition of fresh DF.…”

Section: Introductionmentioning

confidence: 99%

Comparative Studies of ENDF/B-6.8, JEF-2.2 and JENDL-3.2 Data Libraries by Monte Carlo Modeling of High Temperature Reactors on Plutonium Based Fuel Cycles

Talamo

Gudowski

Cetnar

2004

Journal of Nuclear Science and Technology

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We performed a numerical comparative analysis of the burnup capability of the Gas Turbine-Modular Helium Reactor (GT-MHR) by the Monte Carlo Continuous Energy Burnup Code (MCB). The MCB code is an extension of MCNP that includes the burnup implementation; it adopts continuous energy cross sections and it evaluates the transmutation trajectories for over 2,400 decaying nuclides. We equipped the MCB code with three different nuclear data libraries: JENDL-3.2, JEF-2.2 and ENDF/B-6.8 processed for temperatures from 300 to 1,800 K.The GT-MHR model studied in this paper is fueled by actinides coming from the Light Water Reactors waste, converted into two different types of fuel: Driver Fuel and Transmutation Fuel. The Driver Fuel supplies the fissile nuclides needed to maintain the criticality of the reactor, whereas the Transmutation Fuel depletes non-fissile isotopes and controls reactivity excess. We set the refueling and shuffling period to one year and the in-core fuel residency time to three years.The comparative analysis of the MCB code consists of accuracy and precision studies. In the accuracy studies, we performed the burnup calculation with different nuclear data libraries during the year at which the refueling and shuffling schedule set the equilibrium of the fuel composition. In the precision studies, we repeated the same simulations 20 times with a different pseudorandom number stride and the same nuclear data library.

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Project of the GT-MHR high-temperature helium reactor with gas turbine

Cited by 78 publications

References 0 publications

Evaluation of high temperature gas reactor for demanding cogeneration load follow

Evaluation of high temperature gas reactor for demanding cogeneration load follow

COMBINED ACTIVE/PASSIVE DECAY HEAT REMOVAL APPROACH FOR THE 24 MWt GAS-COOLED FAST REACTOR

Comparative Studies of ENDF/B-6.8, JEF-2.2 and JENDL-3.2 Data Libraries by Monte Carlo Modeling of High Temperature Reactors on Plutonium Based Fuel Cycles

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