GOST R 59430-2021 PDF

Full title and description

GOST R 59430-2021 — "Устройства внутрикорпусные водо-водяного энергетического реактора. Расчет на прочность на постпроектных стадиях" (Pressure vessel internals of water-water power reactor — Strength analysis at the post-design stages). The standard sets requirements and methods for justifying the strength and structural integrity of reactor internal components at post-design (operational/assessment) stages, taking into account changes of material properties under service conditions.

Abstract

This national Russian standard provides a framework and calculation procedures for strength assessment of WWER (water-water energetic reactor) internal devices during post-design evaluations. It defines critical-event analyses (fatigue crack initiation, corrosion cracking, radiation creep and embrittlement, defect growth, unstable crack propagation, loss of load-bearing capacity, unacceptable geometric changes and exhaustion of deformation capacity), rules for determining a design defect and methods to assess acceptability of components subject to operational degradation and dynamic loads.

General information

• Status: Active national standard (in force).
• Publication date: Approved 20 October 2021; brought into effect 01 January 2022.
• Publisher: Published under the authority of the Federal Agency for Technical Regulation and Metrology (Rosstandart); printed/issued by FGBU "RST" (Russian Standard), 2021.
• ICS / categories: OKC/ICS area: 27.120.10 (reactor technology / nuclear engineering — reactor technology).
• Edition / version: Edition 2021 (first introduction; designation ГОСТ Р 59430-2021).
• Number of pages: 82 pages.

Scope

The standard applies to internal reactor components of water-water power reactors (WWER) that fall under federal regulations for the use of atomic energy. It is intended for post-design strength justification (assessment and re-evaluation during operation or after modifications), accounting for operationally induced changes in material properties and for dynamic and accident-related load scenarios.

Key topics and requirements

• General provisions and definitions for post-design strength analyses.
• Conditions and acceptance criteria for demonstrating strength under normal operation and deviations from normal operation.
• Analysis procedures for critical events: fatigue crack initiation, corrosion-assisted cracking, radiation-induced creep and embrittlement, and other degradation mechanisms.
• Methods for defining and sizing a calculation/design defect and rules for assessing defect growth (fatigue, corrosion cracking, radiation creep).
• Criteria and procedures for analysing unstable crack growth and loss of load-bearing capacity.
• Assessment of permissible dimensional changes and limits on exhaustion of material deformation capacity.
• Consideration of dynamic loading effects and justification of structural integrity under transient and accidental scenarios.

Typical use and users

Used by nuclear power plant engineering and safety organizations, structural integrity and fitness-for-service assessors, reactor component designers and licensors, maintenance and life‑extension teams, regulatory authorities and technical committees responsible for reactor safety and conformity assessment (standard developed with input from TC 322 — Atomic engineering).

Related standards

The standard references and aligns with other national normative documents for the use of atomic energy and related GOST/R documents (examples include standards on measurement systems and conformity assessment in the atomic energy field and material/radiation property standards cited in its normative references). It was developed with participation of the Central Research Institute of Structural Materials ("Prometey") of the Kurchatov National Research Centre (NIIC "Prometey") and technical committee TC 322.

Keywords

WWER, pressure vessel internals, reactor internals, post-design strength analysis, fitness-for-service, defect growth, fatigue, corrosion cracking, radiation creep, embrittlement, structural integrity, TC 322.

FAQ

Q: What is this standard?

A: It is a Russian national standard (designation ГОСТ Р 59430-2021) that sets requirements and calculation methods for strength assessment of water-water reactor internal components at post-design stages; approved 20 Oct 2021 and effective from 01 Jan 2022.

Q: What does it cover?

A: It covers procedures for demonstrating the strength and acceptability of reactor internals under operational degradation and dynamic/accident loadings, including analyses of crack initiation and growth mechanisms (fatigue, corrosion-assisted cracking), radiation effects (creep and embrittlement), unstable crack propagation, loss of load-bearing capacity and unacceptable dimensional changes.

Q: Who typically uses it?

A: Nuclear plant engineers, structural integrity assessors, maintenance and life‑extension groups, regulatory bodies, technical committees and organizations involved in assessment and repair of reactor internal components.

Q: Is it current or superseded?

A: As published it was introduced on 01 January 2022 and is listed as an active (in‑force) standard; no replacement or cancellation was indicated at the time of publication.

Q: Is it part of a series?

A: It was developed within the framework of standards and normative documents for the use of atomic energy and prepared with input from TC 322 (Atomic engineering). It complements other GOST/R documents and federal rules governing reactor technology and material behaviour under irradiation and operation.

Q: What are the key keywords?

A: Pressure vessel internals, WWER, post-design strength, defect growth, fatigue, corrosion cracking, radiation creep, embrittlement, structural integrity, fitness-for-service.