Development of Key Technologies for Nuclear Hydrogen
Description
VHTR Design Technology Development - Improvement of technology readiness level(TRL 4-5) of design analysis codes by developing inherent codes, verifying them to basic phenomena, issuing software verification and validation reports - Introducing an improved RCCS design concept by analysing existing designs and accessing its validity. VHTR Essential Technology Development - Development of technologies for high temperature experiments and bench-scale components tests in a ways of installing self-designed and manufactured Alloy617 printed-circuit heat exchangers and performing very high temperature test above 900℃ in the helium experimental loop - Validation of passive safety of a reactor cavity cooling system by constructing a 1/4-scale test facility and conducting its performance tests - Development of manufacturing, surface modification, and analysis technology of printed-circuit heat exchangers by fabricating a trial prototype and testing the performance - Assessment tests of candidate nuclear graphites for oxidation and fracture characteristics and high temperature metals for creep and crack-growth characteristics. TRISO Fuel Technology Development - Development of a manufacturing process of UCO kernels and manufacture of a trial-prototype - Performance evaluation of UO2-SiC TRISO fuels through post irradiation examinations - Manufacture of a safety simulation test device and assessment of the validity by an adsorption test - Verification and validation of the fuel performance analysis code(COPA) by using experimental data and international code-benchmarks. Nuclear Hydrogen Interface Technologies - Development of a dynamic simulation code for SI hydrogen production process and production of process evaluation data for a scale-up SI process - Economic evaluation of nuclear hydrogen production system and building the database. SI Thermo-Chemical Hydrogen Production Process Essential Technologies - Construction of 50L/hr-scale SI thermo-chemical integral test facility and completion of 8-hr demonstration test - Development of core technology for scale-up SI process and production of basic design data. Plant System Point Design - Conduction of the point design of 350MWth reactor and plant system - Review of design specification and manufacturing possibility of main components(HX, circulator) - Completion of pre-evaluation report for demonstration plant.
Availability note (English)
Also available from KAERIFiles
49108304.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 285 p.
- Report number
- KAERI/RR--4228/2016
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 49108304
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BENCHMARKS; CRACKS; CREEP; DESIGN; HEAT EXCHANGERS; HYDROGEN; HYDROGEN PRODUCTION; SAFETY; SIMULATION; VERIFICATION; VHTR REACTOR
- Descriptors DEC
- ELEMENTS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MECHANICAL PROPERTIES; NONMETALS; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 8 refs, 130 figs, 16 tabs