Status of ASTRID Nuclear Island Design and Future Trends
Creators
- 1. AREVA NP, Lyon (France)
- 2. CEA, Saint-Paul-Lez-Durance (France)
Description
In the frame of the French ASTRID project led by CEA, AREVA NP is in charge of the design studies of the whole Nuclear Island. The conceptual design was completed end of December 2015 with the issuance of a large amount of engineering files (few thousands). The design of ASTRID intends to cope with GEN IV objectives regarding the new reactor concepts and includes ambitious performances to deal with concerning safety and availability for instance. Thus, numerous technical challenges were faced and successfully managed by AREVA NP during the conceptual design phase dealing with: - Deployment of design process based on System Engineering standards, - Selection of adequate architectures and design justification (at the conceptual level stage) for the various main systems and components: primary circuit, secondary loops, decay heat removal systems, fuel handling and component handling systems, I&C platforms, electrical systems, general layout of nuclear island building etc. Throughout the design progress, AREVA NP experimented new approaches in terms of management of innovations, advanced numerical simulations, management of large CAD models and the related interfaces with the other industrial partners, introduction of Virtual Reality tools to enhance the complexity mastering of the layout. In addition, this paper describes the main technical achievements regarding the NI and main systems or component definition at the end of the conceptual design phase. Future trends for the design of the NI are presented in terms of evolution of the technical configuration and enhancement of the engineering tools. (author)
Additional details
Identifiers
Publishing Information
- Publisher
- IAEA
- Imprint Place
- Vienna (International Atomic Energy Agency (IAEA))
- ISBN
- 978-92-0-108618-1
- Imprint Title
- Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17). Proceedings of an International Conference. Companion CD-ROM
- Imprint Pagination
- [1 CD-ROM]
- Series
- Proceedings Series
- Journal Page Range
- 9 p.
- ISSN
- 0074-1884
Conference
- Title
- International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development
- Acronym
- FR17
- Dates
- 26-29 Jun 2017
- Place
- Yekaterinburg (Russian Federation)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51006343
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; CEA; COMPUTERIZED SIMULATION; FAST REACTORS; NUCLEAR FUELS; SECONDARY COOLANT CIRCUITS; SODIUM COOLED REACTORS
- Descriptors DEC
- COOLING SYSTEMS; ENERGY SOURCES; ENERGY SYSTEMS; EPITHERMAL REACTORS; FRENCH ORGANIZATIONS; FUELS; LIQUID METAL COOLED REACTORS; MATERIALS; NATIONAL ORGANIZATIONS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR MATERIALS; REACTORS; REMOVAL; SIMULATION
Optional Information
- Notes
- 1 ref., figs.
- Secondary number(s)
- IAEA-CN--245-528