Experiments on the load following behaviour of PWR fuel rods

Fischer, G.J.; Sontheimer, F.; Ruyter, I.; Markgraf, J. F. W.

doi:10.1016/0029-5493(88)90231-2

Cited by 2 publications

(1 citation statement)

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“…Of the various types of nuclear reactors investigated to perform load follow [8][9][10][11], only commercial PWRs mainly in France have practiced it by moving ''gray rods'' in the core. Moreover, these investigations focused exclusively on power generation and involved direct cycling of reactor thermal power, e.g.…”

Section: Introductionmentioning

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: Introductionmentioning

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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Simulation of load following mode of operation for a natural circulation pressure tube type BWR

et al. 2011

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A new nuclear power reactor under design study is a vertical pressure tube type boiling light water cooled and heavy water moderated. One of the passive design features of this reactor is the heat removal through natural circulation of primary coolant at all power level with no primary coolant pumps. Nuclear plants are mainly base load units, but the proposed plant with various advance features has to operate in load following mode i.e. Reactor follows Turbine (in a limited range). In this mode, any alteration in turbine load results in the steam pressure change. The steam pressure error is fed to the Reactor Regulating System (RRS), which changes the reactor power to control the system pressure. To study this mode of plant operation, a plant simulation model with the feedbacks from various controllers has been developed using the RELAP5 code. This integrated plant model has been used for simulating the load-varying scenario for a change in plant load. All the process dynamics, modeling, design verification and performance issues are discussed in this paper.

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Experiments on the load following behaviour of PWR fuel rods

Cited by 2 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

Simulation of load following mode of operation for a natural circulation pressure tube type BWR

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