Method for obtaining samples for measuring the distribution of nuclear fuel and its fission products in HTR fuel particles
Description
To optimize the construction and technology for fabrication of HTR fuel particles it is necessary to have experimental information both on the starting technological contamination of the protective coatings of the fuel particles with the fissioning material and the distribution of the nuclear fuel and fission products in samples subjected to reactor tests. The difficulties in performing such studies are caused by the following: the smaller sizes of the fuel particles (the diameter is less than 1.5 mm and the thickness of the coatings ranges from 10 to 100 μm); the physicochemical stability of the materials of the fuel particles (uranium and thorium oxides and carbides, silicon and zirconium carbides, pyrocarbon); high radioactivity; and extremely high gradient of the concentration of fuel and fission products in the protective coatings. The basic idea tested here consists of the following: a laser beam interacts with the surface of a sample rotating chaotically in a stream of gas, a thin spherical layer of material is vaporized, and the vaporized material is deposited on a sampling collector for further analysis
Additional details
Publishing Information
- Journal Title
- Soviet Atomic Energy
- Journal Volume
- 66
- Journal Issue
- 3
- Journal Page Range
- p. 211-213.
- ISSN
- 0038-531X
- CODEN
- SATEAZ
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24038679
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S38: RADIATION CHEMISTRY, RADIOCHEMISTRY AND NUCLEAR CHEMISTRY;
- Resource subtype / Literary indicator
- Translation
- Descriptors DEI
- AEROSOLS; CESIUM 137; DESIGN; EVAPORATION; FILTRATION; FISSION PRODUCTS; FLASH HEATING; FLOWSHEETS; FUEL PARTICLES; GAMMA SPECTROSCOPY; LASERS; NEUTRON ACTIVATION ANALYSIS; NUCLEAR FUELS; PERFORMANCE; PROTECTIVE COATINGS; PYROLYTIC CARBON; RADIOMETRIC ANALYSIS; SAMPLE PREPARATION; SAMPLING; SILICON CARBIDES; TEST FACILITIES; THORIUM CARBIDES; THORIUM OXIDES; URANIUM CARBIDES; URANIUM OXIDES; URANIUM 235; VAPORS; ZIRCONIUM CARBIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ACTIVATION ANALYSIS; ALPHA DECAY RADIOISOTOPES; AMPLIFIERS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CARBIDES; CARBON; CARBON COMPOUNDS; CESIUM ISOTOPES; CHALCOGENIDES; CHEMICAL ANALYSIS; COATINGS; COLLOIDS; DIAGRAMS; DISPERSIONS; ELEMENTS; ENERGY SOURCES; EQUIPMENT; EVEN-ODD NUCLEI; FLUIDS; FUELS; GASES; HEATING; HEAVY NUCLEI; INFORMATION; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTO; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS; MINUTES LIVING RADIOISOTOPES; NONDESTRUCTIVE ANALYSIS; NONMETALS; NUCLEI; ODD-EVEN NUCLEI; OXIDES; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; QUANTITATIVE CHEMICAL ANALYSIS; RADIOACTIVE MATERIALS; RADIOISOTOPES; REACTOR MATERIALS; SEPARATION PROCESSES; SILICON COMPOUNDS; SOLS; SPECTROSCOPY; SPONTANEOUS FISSION RADIOISOTO; THORIUM COMPOUNDS; TRANSITION ELEMENT COMPOUNDS; URANIUM COMPOUNDS; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES; ZIRCONIUM COMPOUNDS
Optional Information
- Notes
- Cover-to-cover Translation of Atomnaya Energy (USSR).