A Study on Very High Temperature Gas-cooled Reactor System Concept
Description
This study consists of two main scopes; the development of the VHTR systems concept for a nuclear process heat (750oC) and a nuclear hydrogen (950 .deg. C) and, the establishment of the demonstration project plan of VHTR systems. As part of the VHTR systems concept study, 1) plant design and functional requirements for both commercial-scale nuclear process heat and nuclear hydrogen systems were developed, 2) design concepts, layout and operating parameters of reactor and plant systems were optimized, 3) design concepts of key high-temperature components and materials were investigated and assessed for their manufacturing and procurement and, 4) design concepts of underground reactor building, radio-waste management and radiation protection were evaluated. In parallel, design analysis systems of reactor and plant systems were constructed and applied for performance analysis and, a system concept of a demonstration plant has been developed and suggested. As part of the demonstration project plan, commercial-scale plant concepts of both nuclear process heat and nuclear hydrogen systems were first selected reflecting market needs and opinions of potential customers and vendors and, then, the economic feasibility study was carried out. Based on them, project structure and strategy of the demonstration project and subsequent commercialization project were established together with relevant business model. Demonstration project plan was developed reflecting opinions of potential vendors of plant design and construction in order to prepare for the demonstration of commercial-scale plant design, function and safety and for subsequent commercialization. The project plan includes not only the project structure, schedule, budget and the project strategies to secure project financing, government support, site and licensing but also the technology development and validation plan required in the process of licensing of the demonstration plant. Depth of the study was at a level of concept development enough for launching the following demonstration project. KAERI took the lead of the study shared by industry participants, POSCO/KONES, Hyundai Engineering and Construction (HDEC), Hyundai Heavy Industries (HHI), Hyundai Engineering (HEC) and STX Heavy Industries who are potential customers and vendors. Work scopes were shared based on expertise of participating organizations; reactor system by KAERI, hydrogen production system by POSCO/KONES, process heat system by HDEC/HEC, reactor building by HDEC, high temperature components and materials by HHI and STX, rad-waste management and economics by KONES. Demonstration project plan and business model was jointly developed by participating organizations in order for practicality and credibility.
Availability note (English)
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49108171.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 648 p.
- Report number
- KAERI/RR--3869/2014
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 49108171
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DESIGN; ECONOMICS; HYDROGEN; HYDROGEN PRODUCTION; KAERI; MANUFACTURING; RADIATION PROTECTION; RADIOACTIVE WASTE MANAGEMENT; VHTR REACTOR
- Descriptors DEC
- ELEMENTS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; KOREAN ORGANIZATIONS; MANAGEMENT; NATIONAL ORGANIZATIONS; NONMETALS; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS; WASTE MANAGEMENT
Optional Information
- Notes
- 148 refs, 371 figs, 221 tabs