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Coolant Chemistry Control and Effects on Fuel Reliability in Pressurized Heavy Water Reactors

Report of a Technical Meeting

IAEA TECDOC No. 1942
English IAEA-TECDOC-1942 978-92-0-134021-4
126 3 18.00 2021

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Description

Providing useful information on optimized chemistry control for pressurized heavy water reactors (PHWRs), this publication presents up to date knowledge on the topic including corrosion phenomena observed in the primary heat transport system and consequent effects on fuel reliability in PHWRs. Specifically, it describes the national practices on coolant chemistry control under various operating conditions and research and development programmes aiming to understand the corrosion phenomena (formation and transport) and related chemistry control. Crud deposit on the fuel cladding, the influence on fuel fitness-for-service in the primary heat transport system, as well as the technical basis for remedial actions to ensure reliable fuel performance in PHWRs are considered.

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Keywords

Coolant, Chemistry, Control, Effect, Fuel, Reliability, PHWR, Pressurized Heavy Water Reactor, Optimized Chemistry, Corrosion Phenomena, Heat Transport, Fuel Reliability, Operating Conditions, R&D, Research, Development, Formation, Transport, Chemistry Control, Fuel Deposit, Fuel Cladding, Fuel Performance, Materials, Corrosion, Corrosion Deposit, Corrosion Fuel, Uranium, Uranium Fuel, Power Reactor Operator, Reactor, PWR, Pressurized Water Reactor, FFS, Fitness For Service, Fuel Fitness, Lithium, Hydrogen, Fuel Bundling, Fuel Cycle, National Practice, Coolant Chemistry Control, Management, Knowledge Retention, Technical Opinion, Observation, PHTS Corrosion, Technical Basis, Remedial Action, AOO, Anticipated Operational Occurrence, DBA, Design Basis Accident, LWR, Light Water Reactor, NPP, Nuclear Power Plant, WANO, World Association of Nuclear Operators, OPEX, Operational Experience

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