Abstract

Chinese large-capacity advanced PWR under construction in China is a new and indispensable reactor type in the developing process of NPP fields. At the same time of NPP construction, accident sequences prediction and operators training are in progress. Since there are some possible events such as feedwater pumps trip in secondary circuit may lead to severe accident in NPP, training simulators and engineering simulators of CI are necessary. And, with an increasing proportion of nuclear power in China, NPP will participate in regulating peak load in power network, which requires accuracy calculation and control of secondary circuit. In order to achieve real-time and full scope simulation in the power change transient and accident scenarios, RELAP5/MOD 3.4 code has been adopted to model the secondary circuit for its advantage of high calculation accuracy. This paper describes the model of steady state and turbine load transient from 100% to 40% of secondary circuit using RELAP5 and provides a reasonable equivalent method to solve the calculation divergence problem caused by dramatic two-phase condition change while guaranteeing the heat transfer efficiency. The validation of the parameters shows that all the errors between the calculation values and design values are reasonable and acceptable.

Highlights

  • Speeding up the development of nuclear power is an inevitable way to solve the energy crisis and environmental problems caused by pollution of fossil energy

  • This paper describes the model of steady state and turbine load transient from 100% to 40% of conventional island (CI)

  • All calculation values are compared with nominal design values, and the errors between them are less than 2%

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Summary

Introduction

Speeding up the development of nuclear power is an inevitable way to solve the energy crisis and environmental problems caused by pollution of fossil energy. Some accident scenarios have been studied using SASSYS such as closure of the turbine admission valve Another code called NATDEMO developed by Argonne National Laboratory is special for EBR-II, including primary, feedwater, and steam systems [2]. Another code named DSNP provides a full scope simulation of power plant based on component or system model in libraries, which are continually updated with new, improved, and verified modules [3]. This model provides an easy interface with nuclear island system and a basic simulation for future accident analysis

Secondary Circuit Model Description
B: Branch
Findings
Validation and Discussion
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