D. J. LEE, J. I. KIM. K. K. KIM,

M. H. CHANG, K. S. MOON

Korea Atomic Energy Research Institute,

Taejon, Republic of Korea

Abstract

An integral reactor concept for nuclear cogeneration plant is being developed at KAERI as an attempt to expand the peaceful utilization of well established commercial nuclear technology and related industrial infrastructure such as desalination technology in Korea. Advanced technologies such as intrinsic and passive safety features are implemented in establishing the design concepts to enhance the safety and performance. Research and development including laboratory-scale tests are concurrently underway to evaluate the characteristics of various passive safety concepts and provide the proper technical data for the conceptual design. This paper describes the preliminary safety and design concepts of the advanced integral reactor. Salient features of the design are hexagonal core geometry, once-through helical steam generator, self-pressurizer, and seismic resistant fine control CEDMs, passive residual heat removal system, steam injector driven passive containment cooling system.

1.0 INTRODUCTION

The drought experienced due to the climatic anomalies and the worsening level of pollution have reduced inland water resources significantly for a number of years. A nuclear co-generation plant which can be used for sea water desalination as well as electricity generation can provide a solution in some coastal countries such as Korea and middle east nations. In this regard, Korea Atomic Energy Research Institute (KAERI) has undertaken a study for the development of advanced integral reactor for the application to these purposes as an attempt to expand the peaceful utilization of nuclear energy.

Most of power reactors that are currently in operation and under development have loop type configurations which enable large-scale power output and thus provide economical power generation. On the other hand, integral reactors receive a wide and strong attention due to its inherent characteristics of enhancing the reactor safety’ and performance through the removal of pipes connecting major primary components. Small and medium reactors with integral configurations of major primary components are actively being developed in many countries. The design concepts of those reactors vary with the purposes of application.

KAERI has been putting efforts to research and develop new and elemental technologies for the implementation into the advanced reactors. In parallel with those efforts, an advanced integral PWR with implementation of those technologies as well as passive safety features is under conceptual development.

The reactor power of 300 MWt is considered as suitable size for energy supply to the industrial complexes, remotely located islands, and especially isolated area. The reactor core is conceptually designed with no soluble boron and hexagonal fuel assemblies to enhance the opertional flexibility and to improve the fuel utilization. The reactor safety system primarily functions in a passive manner when required.

This paper describes the conceptual design features of the advanced integral reactor under development at KAERI, and also important R&D subjects concurrently in progress in order to prove and confirm the technical feasibility of the design concepts.