Published August 1989
| Version v1
Journal article
Examining fuel behaviour in longer operating cycles
Creators
Description
A program of in-pile investigations of fuel assmeblies (FA) produced by the Combustion Engineering company and used in the PWR reactors is delivered. Factors affecting FA reliability are presented, structures with high wear resistance are described. Results of studying the FA with fuel of low enrichment and temperature and irradiation effects on tensile properties of fuel cans made of zircaloy-4 are presented
Additional details
Additional titles
- Original title (Russian)
- Поведение TVEhLOV при увеличении продолжительности циклов облучения
Publishing Information
- Journal Title
- Atomnaya Tekhnika za Rubezhom
- Journal Issue
- no.8
- Series
- At. Tekh. Rubezhom.
- ISSN
- 0320-9326
- CODEN
- ATRUA
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- USSR
- INIS RN
- 21024374
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Translation
- Descriptors DEI
- BURNUP; DESTRUCTIVE TESTING; FRETTING CORROSION; FUEL ASSEMBLIES; FUEL CANS; FUEL ELEMENT FAILURE; NUCLEAR FUELS; POST-IRRADIATION EXAMINATION; PWR TYPE REACTORS; SPACERS; TENSILE PROPERTIES
- Descriptors DEC
- ACCIDENTS; CHEMICAL REACTIONS; CORROSION; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MATERIALS; MATERIALS TESTING; MECHANICAL PROPERTIES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR MATERIALS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Translation from English.