| Display title | Engineering:Very-high-temperature reactor |
| Default sort key | Very-high-temperature reactor |
| Page length (in bytes) | 14,574 |
| Namespace ID | 3034 |
| Namespace | Engineering |
| Page ID | 310929 |
| Page content language | en - English |
| Page content model | wikitext |
| Indexing by robots | Allowed |
| Number of redirects to this page | 0 |
| Counted as a content page | Yes |
| Page image |  |
| HandWiki item ID | None |
| Edit | Allow all users (infinite) |
| Move | Allow all users (infinite) |
| Page creator | imported>John Stpola |
| Date of page creation | 20:10, 1 August 2023 |
| Latest editor | imported>John Stpola |
| Date of latest edit | 20:10, 1 August 2023 |
| Total number of edits | 1 |
| Recent number of edits (within past 90 days) | 0 |
| Recent number of distinct authors | 0 |
Description | Content |
Article description: (description)
This attribute controls the content of the description and og:description elements. | The very-high-temperature reactor (VHTR), or high-temperature gas-cooled reactor (HTGR), is a Generation IV reactor concept that uses a graphite-moderated nuclear reactor with a once-through uranium fuel cycle. The VHTR is a type of high-temperature reactor (HTR) that can conceptually have an outlet... |
