Head-end reprocessing studies with irradiated HTGR-type fuels. III. Studies with RTE-7: TRISO UC$sub 2$-TRISO ThC$sub 2$
Head-end reprocessing studies on irradiated Fort St. Vrain type HTGR fuel (TRISO coated UC$sub 2$-TRISO coated ThC$sub 2$) were performed. Fuel sticks were burned quiescently in oxygen at 750$sup 0$C, the ash was screened to separate the fissile SiC-coated particles from the fertile SiC-coated particles, each particle fraction was crushed and burned separately in oxygen, and the secondary burner ash products were leached. These studies concentrated on the release of radionuclides to the burner off-gases after passing through a 20-$mu$ m sintered metal frit held at 500$sup 0$C. Fission product and heavy metal inventories were made on the process gaseous, liquid, and solid streams. Experimental results are compared with pre-irradiation average fuel stick compositions and with calculated fission product inventories. (auth)
- Research Organization:
- Oak Ridge National Lab., Tenn. (USA)
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-33-009001
- OSTI ID:
- 4139386
- Report Number(s):
- ORNL--5090
- Country of Publication:
- United States
- Language:
- English
Similar Records
SiC-fission product reactions in HTGR TRISO UC/sub 2/ and UC/sub x/O/sub y/ fissile fuel: I, kinetics of reactions in a thermal gradient
SiC-fission product reactions in HTGR TRISO UC/sub 2/ and UC/sub x/O/sub y/ fissile fuel: II, reactions under isothermal conditions
Redistribution of radionuclides in irradiated AGR-1 UCO TRISO fuel after 1800 °C safety testing
Conference
·
Wed Oct 31 23:00:00 EST 1979
· J. Am. Ceram. Soc.; (United States)
·
OSTI ID:5648942
SiC-fission product reactions in HTGR TRISO UC/sub 2/ and UC/sub x/O/sub y/ fissile fuel: II, reactions under isothermal conditions
Conference
·
Wed Oct 31 23:00:00 EST 1979
· J. Am. Ceram. Soc.; (United States)
·
OSTI ID:5648894
Redistribution of radionuclides in irradiated AGR-1 UCO TRISO fuel after 1800 °C safety testing
Journal Article
·
Mon Nov 30 19:00:00 EST 2020
· Journal of Nuclear Materials
·
OSTI ID:1661266
Related Subjects
*COATED FUEL PARTICLES-- SORTING
*SPENT FUELS-- HEAD END PROCESSES
*THORIUM CARBIDES-- CHEMICAL COMPOSITION
*URANIUM CARBIDES-- CHEMICAL COMPOSITION
050800* --Nuclear Fuels--Spent Fuels Reprocessing
COMBUSTION
FILTERS
FISSION PRODUCT RELEASE
FISSION PRODUCTS
GASES
HTGR TYPE REACTORS
LIQUIDS
N40450* --Chemistry--Radiochemistry & Nuclear Chemistry-- Reactor Fuel Processing
OXYGEN
RADIOACTIVE WASTES
REPROCESSING
SILICON CARBIDES
SOLIDS
*SPENT FUELS-- HEAD END PROCESSES
*THORIUM CARBIDES-- CHEMICAL COMPOSITION
*URANIUM CARBIDES-- CHEMICAL COMPOSITION
050800* --Nuclear Fuels--Spent Fuels Reprocessing
COMBUSTION
FILTERS
FISSION PRODUCT RELEASE
FISSION PRODUCTS
GASES
HTGR TYPE REACTORS
LIQUIDS
N40450* --Chemistry--Radiochemistry & Nuclear Chemistry-- Reactor Fuel Processing
OXYGEN
RADIOACTIVE WASTES
REPROCESSING
SILICON CARBIDES
SOLIDS