Published 2023 | Version v1
Miscellaneous Open

Assessment of the Safety Approach for Design Extension Conditions and Application of the Concept of Practical Elimination in the Design of Nuclear Power Plants

Description

The objective of this Safety Guide is to provide recommendations for the design of new nuclear power plants related to defence in depth and the practical elimination of plant event sequences that could lead to an early radioactive release or a large radioactive release. It also provides recommendations in relation to design aspects of defence in depth, in particular on those aspects associated with design extension conditions. Since the introduction of the term ''practical elimination'' in the early 90's and the recognition that accident conditions could include design extension conditions without significant fuel degradation and design extension conditions with core melting, those topics have been the subject of extensive discussions and several publications. The purpose of this publication is to facilitate international consensus on the understanding of those topics among regulators and designers and to provide recommendations for their consistent implementation in relevant nuclear power plant designs. In particular, this Specific Safety Guide gives recommendations related to the demonstration of the implementation of the practical elimination concept for those plant event sequences that could lead to an early radioactive release or a large radioactive release, which relies on the physical impossibility or on the high-level confidence that they are extremely unlikely to arise.

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Additional details

Publishing Information

Imprint Pagination
53 p.
Journal Issue
no.SSG-88
Series
IAEA Safety Standards Series
ISSN
1020-525X
Report number
IAEA-PC--8894

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
54064503
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
Descriptors DEI
FUEL DEGRADATION; MELTDOWN; NUCLEAR POWER PLANTS; REACTOR DESIGN; REACTOR SAFETY; RECOMMENDATIONS
Descriptors DEC
ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; DESIGN; NUCLEAR FACILITIES; POWER PLANTS; REACTOR ACCIDENTS; REACTOR LIFE CYCLE; SAFETY; SEVERE ACCIDENTS; THERMAL POWER PLANTS

Optional Information

Notes
International Atomic Energy Agency (IAEA) Preprint; 16 refs., 1 tab.
Secondary number(s)
INIS-XA--23M0511