Published 1989
| Version v1
Book
Low-frequency coolant temperature and neutron flux perturbations
Creators
- 1. Virginia Polytechnic Inst. and State Univ., Blacksburg, VA (United States). Dept. of Mechanical Engineering
Description
This paper describes an on-line noise analysis technique for determining the moderator temperature coefficient (MTC) in a Pressurized Water Reactor (PWR). A year of noise data collected at a 1000 MW commercial PWR is reviewed and correlated with a one-dimensional theoretical model. It is shown that correlations between neutron and core-exit temperature fluctuations can be used to estimate the MTC
Additional details
Publishing Information
- Publisher
- University of Tennessee at Knoxville.
- Imprint Place
- Knoxville, TN (United States)
- Imprint Title
- Proceedings of the 7th power plant dynamics, control and testing symposium
- Imprint Pagination
- vp.
- Journal Page Range
- p. 50.01-50.13.
Conference
- Title
- 7. power plant dynamics, control and testing symposium.
- Dates
- 15-17 May 1989.
- Place
- Knoxville, TN (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23059353
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMMERCIAL SECTOR; COOLANTS; CORRELATIONS; FLUCTUATIONS; MODERATORS; NEUTRON FLUX; ON-LINE MEASUREMENT SYSTEMS; PWR TYPE REACTORS; REVIEWS; SIGNAL-TO-NOISE RATIO; TEMPERATURE COEFFICIENT
- Descriptors DEC
- DOCUMENT TYPES; ENRICHED URANIUM REACTORS; ON-LINE SYSTEMS; POWER REACTORS; RADIATION FLUX; REACTIVITY COEFFICIENTS; REACTORS; THERMAL REACTORS; VARIATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Funding organization
- Electric Power Research Inst., Palo Alto, CA (United States).
- Secondary number(s)
- CONF-890555--.