Microscale Heat Conduction Models and Doppler Feedback
Creators
- 1. North Carolina State Univ., Raleigh, NC (United States)
- 2. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Description
The objective of this project is to establish an approach for providing the fundamental input that is needed to estimate the magnitude and time-dependence of the Doppler feedback mechanism in Very High Temperature reactors. This mechanism is the foremost contributor to the passive safety of gas-cooled, graphite-moderated high temperature reactors that use fuel based on Tristructural-Isotropic (TRISO) coated particles. Therefore, its correct prediction is essential to the conduct of safety analyses for these reactors. Since the effect is directly dependent on the actual temperature reached by the fuel during transients, the underlying phenomena of heat deposition, heat transfer and temperature rise must be correctly predicted. To achieve the above objective, this project will explore an approach that accounts for lattice effects as well as local temperature variations and the correct definition of temperature and related local effects.
Files
47064330.pdf
Files
(1.5 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:d61381239d300831290d49f5db92e84f
|
1.5 MB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- 14 p.
- Report number
- DOE/NEUP--09-843
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 47064330
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCIDENT-TOLERANT NUCLEAR FUELS; DOPPLER COEFFICIENT; FEEDBACK; FORECASTING; HEAT TRANSFER; HTGR TYPE REACTORS; REACTOR SAFETY; SAFETY ANALYSIS; TEMPERATURE DISTRIBUTION; TEMPERATURE RANGE 1000-4000 K; THERMAL CONDUCTION; TIME DEPENDENCE; TRANSIENTS; VARIATIONS
- Descriptors DEC
- ENERGY SOURCES; ENERGY TRANSFER; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HEAT TRANSFER; MATERIALS; NUCLEAR FUELS; REACTIVITY COEFFICIENTS; REACTOR MATERIALS; REACTORS; SAFETY; TEMPERATURE RANGE
Optional Information
- Contract/Grant/Project number
- AC07-05ID14517
- Funding organization
- USDOE Office of Nuclear Energy - NE. Nuclear Energy University Program (NEUP) (United States)
- Secondary number(s)
- OSTIID--1169924