Design of the Reactor Core for Nuclear Power Plants : Specific Safety Guide.

Format:

Book

Author/Creator:

IAEA.

Series:

IAEA Safety Standards

IAEA Safety Standards ; v.SSG-52

Language:

English

Subjects (All):

Nuclear power plants--Design and construction.

Physical Description:

1 online resource (78 pages)

Edition:

1st ed.

Place of Publication:

Havertown : International Atomic Energy Agency, 2019.

Summary:

The reactor core is the central part of a nuclear reactor where nuclear fission occurs. It consists of four basic systems and components: the fuel (including fuel rods and the fuel assembly structure), the coolant, the moderator and the control rods, as well as additional structures such as reactor pressure vessel internals, core support plates, and the lower and upper internal structure in light water reactors. This Safety Guide provides recommendations on meeting the safety requirements established in IAEA Safety Standards Series No. SSR-2/1 (Rev. 1), Safety of Nuclear Power Plants: Design, applied to the design of the reactor core for nuclear power plants. The publication addresses the safety aspects of the core design and includes neutronic, thermohydraulic, thermomechanical and structural mechanical aspects. Other aspects considered are those relating to reactor core control, shutdown and monitoring, and core management.

Contents:

Intro

1. INTRODUCTION

Background

Objective

Scope

Structure

2. GENERAL SAFETY CONSIDERATIONS IN THE DESIGN of THE REACTOR CORE

Management system

Design objectives

Fundamental safety functions

Adequate design based on the concept of defence in depth

Proven engineering practices

Safety assessment in the design process

Features to facilitate radioactive waste management

Design basis for structures, systems and components of the reactor core

Plant states and postulated initiating events

External hazards

Design limits

Safety classification aspects of the reactor core

Engineering design rules

Design for reliability

Operational limits and conditions

Design for safe operation

Reactor core safety analysis

3. SPECIFIC SAFETY CONSIDERATIONS IN THE DESIGN OF THE REACTOR CORE

General

Fuel type

Coolant

Moderator

Neutronic design

Design considerations

Nuclear design limits

Thermohydraulic design

Thermohydraulic design limits

Thermomechanical design of fuel rods and fuel assemblies

Fuel design limits

Mechanical design of core structures and components

Design limits for the mechanical design of core structures and components

Reactor core control, shutdown and monitoring systems

Reactor core control system

Reactor shutdown system

Partial trip system

Operating limits and set points

Core monitoring system

Core management

Core management design limits

Special core configurations

Impact of fuel design and core management on fuel handling, transport, storage, reprocessing and disposal

4. QUALIFICATION AND TESTING

Design qualification

Inspection

Testing including prototype assemblies and lead use assemblies.

REFERENCES

Annex ISUPPLEMENTARY TECHNICAL INFORMATION

Annex II ASPECTS TO BE ADDRESSED IN THE DESIGN OF THE FUEL ROD, FUEL ASSEMBLY, REACTIVITY CONTROL ASSEMBLY, NEUTRON SOURCE ASSEMBLY AND HYDRAULIC PLUG ASSEMBLY

CONTRIBUTORS TO DRAFTING AND REVIEW.

Notes:

Description based on publisher supplied metadata and other sources.

Other Format:

Print version: IAEA Design of the Reactor Core for Nuclear Power Plants

ISBN:

9789201076229

OCLC:

1321806883