The United Kingdom (UK) Small Modular Reactor (SMR) is being developed by a Rolls-Royce led consortium to provide a market driven, affordable, low carbon energy, generation capability. The UK SMR is a Pressurised Water Reactor (PWR) design based on proven technology with a high level of safety achieved through multiple active and passive systems. This paper presents the approach that has been taken in the early design phases of the pressure vessels for the UK SMR. It considers the key design principles e.g. standardisation, simplification and design for manufacture, inspection and assembly which are being applied to enable the cost and lead-time reductions which are necessary for the UK SMR to be a viable alternative to larger conventional nuclear plants. The Reactor Pressure Vessel (RPV) is used as an example to illustrate some of the key design requirements which need to be addressed. Nuclear components are required to be designed and constructed to standards which are commensurate with the significance of the safety functions which they perform. This paper covers the practice established in the UK of designing to Incredibility of Failure for those components with catastrophic failure modes such as the RPV. It describes the additional features including more stringent materials specification and testing, additional defect tolerance studies and the qualification of manufacturing inspections which need to be addressed in the design to satisfy the high reliability claim.
Skip Nav Destination
2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5143-2
PROCEEDINGS PAPER
Approach to UK SMR Component Design
Christopher D. Bell
Christopher D. Bell
Rolls-Royce plc, Derby, UK
Search for other works by this author on:
Christopher D. Bell
Rolls-Royce plc, Derby, UK
Paper No:
ICONE26-81188, V001T13A003; 6 pages
Published Online:
October 24, 2018
Citation
Bell, CD. "Approach to UK SMR Component Design." Proceedings of the 2018 26th International Conference on Nuclear Engineering. London, England. July 22–26, 2018. V001T13A003. ASME. https://doi.org/10.1115/ICONE26-81188
Download citation file:
93
Views
Related Proceedings Papers
Related Articles
The Fabulous Nuclear Odyssey of Belgium
J. Pressure Vessel Technol (June,2009)
Deterministic and Probabilistic Fracture Mechanics Analysis for Structural Integrity Assessment of Pressurized Water Reactor Pressure Vessel
J. Pressure Vessel Technol (June,2016)
The Use of Risk-Based Approaches in Post-Construction Standards
J. Pressure Vessel Technol (August,2000)
Related Chapters
Subsection NG—Core Support Structures
Companion Guide to the ASME Boiler & Pressure Vessel Codes, Volume 1 Sixth Edition
Czech and Slovakian Codes
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition
Development of Nuclear Boiler and Pressure Vessels in Taiwan
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition