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Title: An analytical study of volatile metallic fission product release from very high temperature gas-cooled reactor fuel and core

Abstract

Release characteristics of volatile metallic fission products from the coated fuel particle and the reactor core for a very high temperature gas-cooled reactor during its power operation has been studied using numerical analysis. A computer code FORNAX, based on Fick's diffusion law and the evaporation mass transfer relation, has been developed, which considers, in particular, distribution and time histories of power density, fuel temperature, and failed and degraded fuel particle fractions in the core. Applicability of the code to evaluate the core design has been shown and the following have been indicated on the release of cesium from the reactor: 1. The release from the intact fuel particles by diffusion through their intact coatings shows larger contribution in the total core release at higher temperature. 2. The diffusion release from the intact particle is governed not only by the diffusion in the silicon carbide layer but also by that in the fuel kernel.

Authors:
;
Publication Date:
Research Org.:
Japan Atomic Energy Research Institute, Div. of Power Reactor Projects, Tokai-mura, Ibaraki 319-11 (JP)
OSTI Identifier:
5011703
Resource Type:
Journal Article
Journal Name:
Nucl. Technol.; (United States)
Additional Journal Information:
Journal Volume: 81:1
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 54 ENVIRONMENTAL SCIENCES; COMPUTER CODES; F CODES; HTGR TYPE REACTORS; COATED FUEL PARTICLES; COMPUTERIZED CONTROL SYSTEMS; DESIGN; PERFORMANCE TESTING; TEST FACILITIES; REACTOR CORES; FAILURE MODE ANALYSIS; FISSION PRODUCT RELEASE; ANALYTICAL SOLUTION; CESIUM; DISTRIBUTION FUNCTIONS; MASS TRANSFER; NUMERICAL SOLUTION; ON-LINE MEASUREMENT SYSTEMS; SILICON CARBIDES; SURFACE COATING; TEMPERATURE GRADIENTS; ALKALI METALS; CARBIDES; CARBON COMPOUNDS; CONTROL SYSTEMS; DEPOSITION; ELEMENTS; FUEL PARTICLES; FUNCTIONS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; METALS; ON-LINE SYSTEMS; REACTOR COMPONENTS; REACTORS; SILICON COMPOUNDS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TESTING; 220400* - Nuclear Reactor Technology- Control Systems; 210400 - Power Reactors, Nonbreeding, Otherwise Moderated or Unmoderated; 220100 - Nuclear Reactor Technology- Theory & Calculation; 500300 - Environment, Atmospheric- Radioactive Materials Monitoring & Transport- (-1989)

Citation Formats

Mitake, S, and Okamoto, F. An analytical study of volatile metallic fission product release from very high temperature gas-cooled reactor fuel and core. United States: N. p., 1988. Web.
Mitake, S, & Okamoto, F. An analytical study of volatile metallic fission product release from very high temperature gas-cooled reactor fuel and core. United States.
Mitake, S, and Okamoto, F. 1988. "An analytical study of volatile metallic fission product release from very high temperature gas-cooled reactor fuel and core". United States.
@article{osti_5011703,
title = {An analytical study of volatile metallic fission product release from very high temperature gas-cooled reactor fuel and core},
author = {Mitake, S and Okamoto, F},
abstractNote = {Release characteristics of volatile metallic fission products from the coated fuel particle and the reactor core for a very high temperature gas-cooled reactor during its power operation has been studied using numerical analysis. A computer code FORNAX, based on Fick's diffusion law and the evaporation mass transfer relation, has been developed, which considers, in particular, distribution and time histories of power density, fuel temperature, and failed and degraded fuel particle fractions in the core. Applicability of the code to evaluate the core design has been shown and the following have been indicated on the release of cesium from the reactor: 1. The release from the intact fuel particles by diffusion through their intact coatings shows larger contribution in the total core release at higher temperature. 2. The diffusion release from the intact particle is governed not only by the diffusion in the silicon carbide layer but also by that in the fuel kernel.},
doi = {},
url = {https://www.osti.gov/biblio/5011703}, journal = {Nucl. Technol.; (United States)},
number = ,
volume = 81:1,
place = {United States},
year = {Fri Apr 01 00:00:00 EST 1988},
month = {Fri Apr 01 00:00:00 EST 1988}
}