Performance of fuel failure detection system for coated particle fuels

Journal Article · Mon Apr 01 00:00:00 EST 1985 · IEEE Trans. Nucl. Sci.; (United States)

DOI:https://doi.org/10.1109/TNS.1985.4333576· OSTI ID:5985686

Treada, H; Ohkawa, H; Ohlsu, H; Wakayama, N; Yoshida, H

An experimental system was developed for a study of fuel failure detection (FFD) method for coated particle fuels (CPF's) of a high-temperature gas-cooled reactor. Various performance of the FFD-system were examined using a CPF-irradiation rig in the Japan Material Testing Reactor. By experiments, it was made sure that the counting rates of fission products (FP's), released from the CPF's, change with the reactor-power and the fuel-temperature remarkably even during the normal reactor operation. Also, an ability of the selective detection of only short-life FP-nuclides was studied in relation to the travelling time of the sampling gas. The results showed that the contributions of the short-life FP-nuclides such as Kr-89 and Kr-90 are more than 80 percent to the total FP-counting rate at the shortest travelling time of 120 sec. It is concluded that the selective detection of only the short-life FP-nuclides can be realized by controlling the travelling time properly.

• Research Organization: Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki-ken
• OSTI ID: 5985686
• Journal Information: IEEE Trans. Nucl. Sci.; (United States), Vol. NS-32:2
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COATED FUEL PARTICLES
FAILED ELEMENT DETECTION
FAILED ELEMENT MONITORS
PERFORMANCE TESTING
HTGR TYPE REACTORS
REACTOR SAFETY
COUNTING RATES
FISSION FRAGMENT DETECTION
FISSION PRODUCTS
FUEL ELEMENT FAILURE
JMTR REACTOR
KRYPTON 89
KRYPTON 90
ACCIDENTS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
DETECTION
ENRICHED URANIUM REACTORS
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
INTERMEDIATE MASS NUCLEI
IRRADIATION REACTORS
ISOTOPES
KRYPTON ISOTOPES
MATERIALS
MATERIALS TESTING REACTORS
MEASURING INSTRUMENTS
MINUTES LIVING RADIOISOTOPES
MONITORS
NUCLEI
RADIATION DETECTION
RADIOACTIVE MATERIALS
RADIOISOTOPES
REACTOR ACCIDENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SECONDS LIVING RADIOISOTOPES
TANK TYPE REACTORS
TEST REACTORS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210300 - Power Reactors
Nonbreeding
Graphite Moderated