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

Journal Article · Fri Apr 01 00:00:00 EST 1988 · Nucl. Technol.; (United States)

OSTI ID:5011703

Mitake, S; Okamoto, F

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.

• Research Organization: Japan Atomic Energy Research Institute, Div. of Power Reactor Projects, Tokai-mura, Ibaraki 319-11 (JP)
• OSTI ID: 5011703
• Journal Information: Nucl. Technol.; (United States), Vol. 81:1
• Country of Publication: United States
• Language: English

Related Subjects

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)