Status of Sodium Cooled Fast Reactor Development Program in Korea
- 1. Korea Atomic Energy Research Institute (KAERI), Daejeon (Korea, Republic of)
Description
The Korea Atomic Energy Commission (KAEC) authorized the R&D action plan for the development of the advanced sodium-cooled fast reactor (SFR) and the pyro-processing technologies to provide a consistent direction to long-term R&D activities in December, 2008. This long-term advanced SFR R&D plan was revised by Korea Atomic Energy Promotion Council (KAEPC) in November 2011 in order to refine the plan and to consider the available budget for SFR. The revised milestones include specific design of a prototype SFR by 2017, specific design approval by 2020, and construction of a prototype generation IV SFR (PGSFR) by 2028. The prototype SFR program includes the overall system engineering for SFR system design and optimization, integral V&V tests, and major components development. Based upon the experiences gained during the development of the conceptual designs for KALIMER, the conceptual design of PGSFR has been carried out in 2012 and has been performing a preliminary design since 2013. The first phase of the development of PGSFR has been completed at the end of February 2016 and now going toward the second design phase in 2016. All the design concepts of systems, structures and components (SSCs) have been determined and incorporated into the preliminary safety information document (PSID), which includes basic design requirements, system and component descriptions, and the results of safety analysis for the representative accident scenarios. The PSID will be a base material for a pre-review of the PGSFR safety. The target of the second phase of PGSFR design is to prepare a specific design safety analysis report (SDSAR) by the end of 2017. The SDSAR is equivalent to the conventional preliminary safety analysis report (PSAR) but without the specific site information of the plant. To support the design, various R&D activities are being performed in parallel with design activities, including V&Vs of design codes and system performance tests. (author)
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Additional details
Identifiers
Publishing Information
- Imprint Title
- International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17). Programme and Papers
- Imprint Pagination
- vp.
- Journal Page Range
- 8 p.
- Report number
- IAEA-CN--245
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
- 49085729
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FAST REACTORS; REPUBLIC OF KOREA; SAFETY ANALYSIS; SODIUM COOLED REACTORS
- Descriptors DEC
- ASIA; DEVELOPING COUNTRIES; EPITHERMAL REACTORS; LIQUID METAL COOLED REACTORS; REACTORS
Optional Information
- Contract/Grant/Project number
- Grant 2012M2A8A2008157
- Notes
- 6 refs., 1 fig., 3 tabs.
- Secondary number(s)
- IAEA-CN--245-460