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Title: Microscale Heat Conduction Models and Doppler Feedback

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.
Authors:
 [1] ;  [2]
  1. North Carolina State Univ., Raleigh, NC (United States)
  2. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
OSTI Identifier:
1169924
Report Number(s):
DOE/NEUP--09-843
09-843; TRN: US1600515
DOE Contract Number:
AC07-05ID14517
Resource Type:
Technical Report
Research Org:
North Carolina State Univ., Raleigh, NC (United States); Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE). Nuclear Energy University Program (NEUP)
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; HTGR TYPE REACTORS; THERMAL CONDUCTION; SAFETY ANALYSIS; TEMPERATURE RANGE 1000-4000 K; FEEDBACK; ACCIDENT-TOLERANT NUCLEAR FUELS; HEAT TRANSFER; TIME DEPENDENCE; FORECASTING; TRANSIENTS; VARIATIONS; DOPPLER COEFFICIENT; REACTOR SAFETY; TEMPERATURE DISTRIBUTION