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Heat transfer behaviour and thermohydraulics code testing for supercritical water cooled reactors (SCWRs) - IAEA-TECDOC Series International Atomic Energy Agency
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Heat transfer behaviour and thermohydraulics code testing for supercritical water cooled reactors (SCWRs) - IAEA-TECDOC Series
International Atomic Energy Agency
In order to develop the supercritical water cooled reactor (SCWR) concept, thermohydraulics of supercritical pressure water is one of the most important areas to be clarified. This publication summarizes the outcome of an IAEA coordinated research project (CRP) on this topic.
505 pages
| Mediji | Grāmatas Paperback Book (Grāmata ar mīksto vāku un līmēto muguru) |
| Izlaists | 2014. gada 1. augusts |
| ISBN13 | 9789201076144 |
| Izdevēji | IAEA |
| Lapas | 505 |
| Izmēri | 150 × 220 × 10 mm · 837 g (Svars (aptuveni)) |