Published 1996
| Version v1
Book
Overview of TUF code for CANDU reactors
Creators
- 1. Ontario Hydro Nuclear, Reactor Safety and Operational Analysis Dept., Toronto, Ontario (Canada)
Description
An overview of the TUF code is presented. The important physical parameters used in the following code modules are briefly discussed: reactor control and safety systems; thermal-hydraulics; heat conduction; reactor physics; and system components. The approach for code qualification as an analytical tool for CANDU reactors is described. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 0-919784-47-X
- Imprint Title
- Simulation methods in nuclear engineering
- Imprint Pagination
- 2 v.
- Journal Page Range
- (v.1) [17 p.]
Conference
- Title
- 5. International conference on simulation methods in nuclear engineering
- Dates
- 8-11 Sep 1996
- Place
- Montreal, PQ (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 33018514
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; COMPUTER CODES; LOSS OF COOLANT; REACTOR CONTROL SYSTEMS; REACTOR PHYSICS; REACTOR SAFETY; SYSTEMS ANALYSIS; T CODES; THERMAL CONDUCTIVITY
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTROL SYSTEMS; HEAVY WATER MODERATED REACTORS; PHYSICAL PROPERTIES; PHYSICS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL REACTORS; THERMODYNAMIC PROPERTIES
Optional Information
- Notes
- 26 refs., 1 tab.