Development of coated fuel particle for VHTR reactor
Creators
- 1. Pusat Pengembangan Energi Nuklir - BATAN, Jl. Kuningan Barat, Mampang Prapatan, Jakarta Selatan 12710 (Indonesia)
Description
The VHTR reactor is a high temperature reactor concept with a 1000oC outlet temperature and it is one of IV generation reactor that is being developed. This reactor is developed based on GT-MHR reactor with higher outlet temperature reactor, burn-up and electricity efficiency. Accordingly, material improvement is necessary, such as: SiC in correlation to elevated temperature of 850oC to 1000oC. The SiC layer plays an important role. Beside retaining metallic fission products (Cs-137, Ru-106) released from fuel kernel, it also provides mechanical strength and dimension stability to fuel particle. The ZrC layer can be considered to replace SiC because of its higher temperature capability. ZrC has a melting point of 35400C whereas SiC has a melting point of 1800oC. The ZrC-TRISO coated fuel particle did not fail until ∼6000 seconds at 2200oC heating, while a few percent of the conventional TRISO-coated fuel particles failed already by 2200oC, and almost 100% instantaneously at 2400oC. In the whole temperature range, ZrC layer showed more resistance to chemical corrosion by fission products, especially by palladium (Pd) which is known to corrode the SiC layer. However, The ZrC layer capability to retention of Ru-106 was inferior to SiC. The retention of the other metal fission products such as barium, silver and promethium appears to be better than SiC. (author)
Additional details
Additional titles
- Original title (Indonesian)
- Pengembangan partikel bahan bakar berlapis untuk reaktor VHTR
Publishing Information
- Journal Title
- Jurnal Pengembangan Energi Nuklir
- Journal Volume
- 10
- Journal Issue
- 2
- Journal Page Range
- p. 113-122
- ISSN
- 1410-9816
INIS
- Country of Publication
- Indonesia
- Country of Input or Organization
- Indonesia
- INIS RN
- 46134361
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- FISSION PRODUCTS; FUEL INTEGRITY; FUEL PARTICLES; NUCLEAR FUELS; SILICON CARBIDES; VHTR REACTOR; ZIRCONIUM CARBIDES
- Descriptors DEC
- CARBIDES; CARBON COMPOUNDS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; ISOTOPES; MATERIALS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SILICON COMPOUNDS; THERMAL REACTORS; TRANSITION ELEMENT COMPOUNDS; ZIRCONIUM COMPOUNDS
Optional Information
- Notes
- 12 refs.; 3 tabs.; 4 figs.