SOPHT–A Computer Model for CANDU-PHWR Heat Transport Networks and Their Control
| Autor: | John Skears, Charles Yung Fen Chang |
|---|---|
| Rok vydání: | 1977 |
| Předmět: |
Pressurized heavy-water reactor
Nuclear and High Energy Physics Mathematical model Nuclear engineering chemistry.chemical_element Division (mathematics) Uranium Condensed Matter Physics Nuclear Energy and Engineering chemistry Control system Heat transfer Environmental science Transient (oscillation) Test data |
| Zdroj: | Nuclear Technology. 35:591-602 |
| ISSN: | 1943-7471 0029-5450 |
| DOI: | 10.13182/nt77-a31868 |
| Popis: | A digital computer simulation program, SOPHT, was developed by the Nuclear Generation Division of Ontario Hydro to assist their operating staff to ensure safe, reliable, and economic power generation. The program is used to predict the transient performance for Canadian deuterium uranium pressurized heavy water reactor (CANDU-PHWR) heat transport and steam supply networks together with their associated control systems. The model was verified by test data obtained in an operating plant. Examples are used to review and demonstrate the applications and contributions of this simulation program to plant operations. |
| Databáze: | OpenAIRE |
| Externí odkaz: |
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