Published 1996
| Version v1
Book
GE SBWR stability analysis using TRAC-BF1 1-D kinetics model
Creators
- 1. Pennsylvania State Univ., University Park, PA (United States). Nuclear Engineering Dept.
Description
GE's simplified boiling water reactor, with its unique feature of using natural circulation to remove the heat from the reactor core, is a complicated dynamic system. Previous work by authors using the TRAC-BF1 code and a point kinetics model predicted that an SBWR may experience large amplitude power oscillation under certain low pressure and high power operating conditions. To further confirm the existence of this power oscillation and explore the dynamic spatial reactor power distribution, the TRAC-BF1 1-D kinetics model was used. The results show that an instability exists and the power oscillation starting time and maximum peak power are different from the point kinetics results
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1226-X
- Imprint Title
- ICONE-4: Proceedings. Volume 2: Advanced reactors
- Imprint Pagination
- 637 p.
- Journal Page Range
- p. 527-535.
Conference
- Title
- ASME/JSME international conference on nuclear engineering.
- Acronym
- ICONE 4
- Dates
- 10-13 Mar 1996.
- Place
- New Orleans, LA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27059996
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; HEAT TRANSFER; NATURAL CONVECTION; REACTOR KINETICS; REACTOR OPERATION; REACTOR STABILITY; T CODES; THEORETICAL DATA
- Descriptors DEC
- COMPUTER CODES; CONVECTION; DATA; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; INFORMATION; KINETICS; NUMERICAL DATA; OPERATION; POWER REACTORS; REACTORS; SIMULATION; STABILITY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-960306--.