SOPHT: a computer model for CANDU-PHWR heat transport works and their control
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:7279306
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.
- Research Organization:
- Ontario Hydro, Toronto
- OSTI ID:
- 7279306
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 35:3; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
CANDU TYPE REACTORS
COMPUTER CODES
COOLING SYSTEMS
ENERGY TRANSFER
FLUID FLOW
HEAT TRANSFER
HEAVY WATER MODERATED REACTORS
MATHEMATICAL MODELS
PRESSURE TUBE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
S CODES
THERMAL REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
CANDU TYPE REACTORS
COMPUTER CODES
COOLING SYSTEMS
ENERGY TRANSFER
FLUID FLOW
HEAT TRANSFER
HEAVY WATER MODERATED REACTORS
MATHEMATICAL MODELS
PRESSURE TUBE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
S CODES
THERMAL REACTORS