ULOF Accident Analysis for 300 MWt Pb-Bi Coolled MOX Fuelled SPINNOR Reactor

Ade Gafar Abdullah,Zaki Su’Ud,Rizal Kurniadi,Neny Kurniasih

doi:10.5539/apr.v4n1p91

Ade Gafar Abdullah, Zaki Su’Ud + Show 2 more

Open Access

https://doi.org/10.5539/apr.v4n1p91

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Abstract

In This study the result of investigation through simulation of unprotected loss of flow accident (ULOF) for 300 MWth MOX fuelled small Pb-Bi Cooled non-refuelling nuclear reactors (SPINNOR) are discussed. The two dimensional diffusion calculation combined with transient thermal hydraulic analysis has been employed. The reactor is tank type Pb-Bi cooled fast reactors with steam generator included inside reactor vessel. The simulation begin with steady state calculation of neutron flux, power distribution and temperature distribution across the core, hot and cool pool, and also steam generator. The accident analysis begin with the loss of pumping power. The sequence of analysis is then the transient flow calculation across the core, the core temperature distribution, hot pool and cool pool fluid dynamic calculation and temperature change simulation, and the transient flow and temperature calculation across the steam generator. Then the reactivity feedback calculation is conducted, followed by kinetic calculation, and then the sequence repeated. The results show that the SPINNOR reactor has inherent safety capability against this accident.

Highlights

Since accident of Chernobyl, TMI II and the latest one Fukushima, the attention focuses on safety aspect of nuclear reactors
The reactor is tank type Pb-Bi cooled fast reactors with steam generator included inside reactor vessel
The simulation begin with steady state calculation of neutron flux, power distribution and temperature distribution across the core, hot and cool pool, and steam generator

Summary

Introduction

Since accident of Chernobyl, TMI II and the latest one Fukushima, the attention focuses on safety aspect of nuclear reactors. The SPINNOR (Small Power Reactor, Indonesia, No On-Site Refueling) are concepts of small lead-bismuth cooled nuclear power reactors with fast neutron spectrum that could be operated for more than 15 years without on-site refueling. They are based on the concept of a long-life core reactor developed in Indonesia since early 1990 in collaboration with the Research Laboratory for Nuclear Reactors of The Tokyo Institute of Technology (Zaki, 2007). Some important requisite characteristics are easy operation, easy maintenance, transportability, inherent/passive safety and nuclear proliferation resistance. By the term safe here we mean that reactor is able to survive ULOF (Unprotected Loss of Flow) accident without reactor scram or the help of the operator

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