A study on the thermal expansion characteristics of simulated spent fuel and simulated DUPIC fuel
Description
Thermal expansions of simulated spent PWR fuel and simulated DUPIC fuel were studied using a dilatometer in the temperature range from 298 to 1900 K. The densities of simulated spent PWR fuel and simulated DUPIC fuel used in the measurement were 10.28 g/cm3 (95.35 % of TD) and 10.26 g/cm3 (95.14 % of TD), respectively. Their linear thermal expansions of simulated fuels are higher than that of UO2, and the difference between these fuels and UO2 increases progressively as temperature increases. However, the difference between simulated spent PWR fuel and simulated DUPIC fuel can hardly be observed. For the temperature range from 298 to 1900 K, the values of the average linear thermal expansion coefficients for simulated spent PWR fuel and simulated DUPIC fuel are 1.391 10-5 and 1.393 10-5 K-1, respectively. As temperature increases to 1900 K, the relative densities of simulated spent PWR fuel and simulated DUPIC fuel decrease to 93.81 and 93.76 % of initial densities at 298 K, respectively
Availability note (English)
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Additional details
Publishing Information
- Imprint Pagination
- 20 p.
- Report number
- KAERI/TR--1922/2001
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 33066918
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DENSITY; PWR TYPE REACTORS; SPENT FUELS; TEMPERATURE RANGE; THERMAL EXPANSION; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EXPANSION; FUELS; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; POWER REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 13 refs, 4 figs, 4 tabs