Assessment of Off-Site Consequences Due to Severe Nuclear Accident According to Release Pathway Reduction Mechanisms Using Computer Code

Elsayeda Farid Salem

doi:10.11648/j.ijsqa.20160202.12

Abstract

In order to protect public health and safety from the inadvertent release of radioactive materials, during a reactor accident the defense-in-depth strategy must include; multiple layers of protection, such as prevention of accidents, mitigation features and emergency preparedness program that include measures such as sheltering and evacuation. In the present work RASCAL computer code is going to be used to estimate the offsite consequences of a nuclear sever accident using release pathway reduction mechanisms in order to obtain an appropriate release at a Pressurized Water Reactor (PWR) operating at its full power. The existing plant (systems, equipment) assuming that will be used for accident mitigation. Calculation of the total effective dose associated with this reduction is proposed. The data obtained showed that the spray system is the most effective mechanism to mitigate dose release during the accident.

Highlights

Consideration of severe accidents at a nuclear power plants (NPP) is an essential component of the defense in depth approach used in nuclear safety
A comparison between total effective doses equivalent (TEDE) at different distances away release point for all cases was illustrated in figure 3
The containment spray pump will take suction from the refueling water storage tank and pump the water into spray rings located in the upper part of the containment

Summary

Introduction

Consideration of severe accidents at a nuclear power plants (NPP) is an essential component of the defense in depth approach used in nuclear safety. Computer codes are essential tools for understanding how the reactor and its containment might respond under severe accident conditions. The codes are used as a tool to support engineering judgment, based on which specific measures to mitigate the effects of severe accidents are designed. They are used to determine accident management strategies and for probabilistic safety assessment (PSA). Beyond design basis accidents: Accident conditions will be more severe than a design basis accident It may or may not involve core degradation [1].

RASCAL Computer Code Description

Basic Input Parameters

Scenarios Description

Results and Discussion

Conclusions