Fully-coupled transient simulation for RCS and SPCS of an integral reactor plant

Kang, Han-Ok; Lee, Seong-Wook; Park, Cheon-Tae

doi:10.1016/j.anucene.2009.11.012

Cited by 5 publications

(2 citation statements)

References 9 publications

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“…The MMS has also been used for the purpose of modeling and simulation of nuclear power plants (Kang et al, 2010;Yoon et al, 2000Yoon et al, , 2002Kang et al, 2000;Godbole and Malan, 1991). More technical papers based on the MMS can be found at www.nhancetech.com.…”

Section: Introductionmentioning

confidence: 98%

Experimental and analytical investigations of primary coolant pump coastdown phenomena for the Jordan Research and Training Reactor

Alatrash

Kang

Yoon

et al. 2015

Nuclear Engineering and Design

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Section: Introductionmentioning

confidence: 98%

Experimental and analytical investigations of primary coolant pump coastdown phenomena for the Jordan Research and Training Reactor

Alatrash

Kang

Yoon

et al. 2015

Nuclear Engineering and Design

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“…This puts forward higher requirement for the control system design of IPWR system. Hence, many investigators have focused on the study of the load‐following characteristics and stability of the reactor system .…”

Section: Introductionmentioning

confidence: 99%

Analysis of load-following characteristics for an integrated pressurized water reactor

Xia

Peng

2013

Int. J. Energy Res.

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SUMMARYIntegrated pressurized water reactor (IPWR) usually be equipped with once-through steam generators (OTSGs). The OTSG has many advantages such as simple mechanical structure, smaller size, and higher heat transfer efficiency. It produces superheated steam but with less inventory in its secondary side. The steam pressure is easily affected by steam flow rate or feed water flow rate. This draws more attention to design advanced reactor control system. In this paper, a study has been carried out to analyze the thermal hydraulic performance of an advanced IPWR under steady-state and transient conditions by using a thermal hydraulic safety analysis code Relap5. An effective load-following control system is proposed. The steady-state operating characteristics of IPWR at different load conditions show that the average primary coolant temperature, steam pressure, and coolant mass flow rate are the most important control parameters. Pump frequency conversion strategy and OTSG grouping run strategy are used to study the transient operating characteristics of IPWR. Simulation results of the control system demonstrate its capability in regulating feedwater flow rate and reactor power to follow the change of steam flow rate. According to the results, the OTSG grouping run strategy is optimized to ensure the OTSG operates safely under low load conditions.

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Numerical study on annular tube once-through steam generator using compressible flow model

Wang

Tian

et al. 2012

Annals of Nuclear Energy

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Fully-coupled transient simulation for RCS and SPCS of an integral reactor plant

Cited by 5 publications

References 9 publications

Experimental and analytical investigations of primary coolant pump coastdown phenomena for the Jordan Research and Training Reactor

Experimental and analytical investigations of primary coolant pump coastdown phenomena for the Jordan Research and Training Reactor

Analysis of load-following characteristics for an integrated pressurized water reactor

Numerical study on annular tube once-through steam generator using compressible flow model

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