Published September 1978
| Version v1
Report
Limitation of the uranium content of MTR fuel elements from the technological standpoint of the fuel element manufacturer
Description
Graphs are presented showing the 235U and U contents of fuel elements as a function of fuel volume for Al-U-alloy, UAlsub(x)-Al cermet and U3O8-Al cermet fuels. The present state of technology, the short term and long term development possibilities are described. (author)
Additional details
Publishing Information
- Imprint Title
- Research reactor renewal and upgrading programmes
- Journal Page Range
- p. 307-312.
- Report number
- IAEA--214
Conference
- Title
- Advisory group meeting on research reactor renewal and upgrading programmes.
- Dates
- 23 - 26 May 1978.
- Place
- Vienna, Austria.
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 10485013
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CERMETS; FUEL ELEMENTS; ISOTOPE RATIO; MTR REACTOR; URANIUM; URANIUM 235
- Descriptors DEC
- ACTINIDE NUCLEI; ACTINIDES; ALPHA DECAY RADIOISOTOPES; COMPOSITE MATERIALS; ELEMENTS; ENRICHED URANIUM REACTORS; EVEN-ODD NUCLEI; HEAVY NUCLEI; IRRADIATION REACTORS; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS TESTING REACTORS; METALS; MINUTES LIVING RADIOISOTOPES; NUCLEI; RADIOISOTOPES; REACTOR COMPONENTS; REACTORS; TANK TYPE REACTORS; THERMAL REACTORS; URANIUM ISOTOPES; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES