Pellet-Cladding Interaction (PCI and PCMI): progress in nuclear industry

(ZIRAT27/IZNA22)

Pellet-Cladding Interaction (PCI) and Pellet-Cladding Mechanical Interaction (PCMI) remains an important phenomenon in the modern nuclear reactor fuel engineering. This topic was addressed in detail in ZIRAT-11 Special topical report on PCI issued in 2006. Since then, a substantial development has taken place, such as introduction of new cladding materials and additive fuel pellets. In addition to this, flexible power operation is being considered by many utilities worldwide. This introduces new challenges to the safe and reliable operation of the nuclear fuel. The report discusses up-to-date developments in the above mentioned areas and summarizes the main outcomes of the R&D work performed since 2006.

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Pellet-Cladding Interaction

(ZIRAT11/IZNA6 STR)
PCI has historically resulted in a large number of fuel failures in BWRs but also to some extent in PWRs. The introduction of various remedies such as power change operation restrictions and liner/barriers in BWRs has reduced the number of PCI failures. However, there are some recent fuel failures in both BWRs and PWRs that has put the PCI failure mode in focus again. The objective of this report is to give a better understanding of the PCI mechanisms, pertinent methods to test PCI performance and PCI remedy technology may improve fuel reliability and reactor safety.

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Pellet Cladding Interaction, PCI, in PWRs/VVERs/BWRs (ZIRAT30/IZNA25)

The Special Topic Report on PCI-SCC provides a comprehensive state-of-the-art review of Pellet-Cladding Interaction assisted by Stress Corrosion Cracking (PCI-SCC), one of the most important fuel reliability and operational flexibility challenges in modern nuclear power plants. The report consolidates decades of international R&D, operating experience, experimental results, and recent advances in modeling and fuel design related to PCI-SCC.

The report covers the fundamental mechanisms behind PCI-SCC, laboratory testing techniques, in-reactor experience, fuel and cladding design improvements, advanced modeling approaches, and operational methodologies for flexible power operation and load-following conditions. Special attention is given to modern fuel designs, fuel conditioning and deconditioning strategies, Accident Tolerant Fuel (ATF) developments, and the increasing importance of PCI-SCC under evolving grid demands and extended reduced power operation (ERPO).

The report also highlights recent progress in mechanistic understanding, post-irradiation examination techniques, simulation tools, manufacturing quality improvements, and operational guidelines used internationally to manage PCI-SCC risks.
The report provides utilities, fuel vendors, regulators, and technical specialists with an up-to-date technical reference on PCI-SCC, combining operating experience, recent research, advanced modelling developments, and practical operational guidance to support improved fuel reliability, operational flexibility, and informed decision-making for current and future reactor operation.

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Mechanical Properties of Zirconium Alloys

(ZIRAT6/IZNA1 STR)
Adequate mechanical properties are crucial for satisfactory fuel assembly performance: 1) in-pile under normal operation, anticipated operational occurrences and accident conditions as well as, 2) under intermediate storage conditions. The objective of this report is to provide the basic understanding of the mechanical properties of the fuel components that are crucial for the fuel in-pile performance.

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MECHANICAL PROPERTIES

This report is intended to provide basic understanding on the mechanical properties of zirconium alloys, stainless and ferritic steels and nickel alloys. The information can then be used by customers to evaluate their components.

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