Extension of lifespan of graphite in fuel blocks of high-temperature gas-cooled reactors as the resource for ensuring design values of nuclear fuel burn-up
High-temperature gas-cooled reactor (HTGR) is one of promising candidates for new generation of nuclear power reactors. This type of nuclear reactor is characterized with the following principal features: highly efficient generation of electricity (thermal efficiency of about 50%);...
| Main Authors: | , , , |
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| Format: | Article |
| Language: | English |
| Published: |
National Research Nuclear University (MEPhI)
2019-12-01
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| Series: | Nuclear Energy and Technology |
| Subjects: | |
| Online Access: | https://nucet.pensoft.net/article/48391/download/pdf/ |