Published 2003
| Version v1
Book
Studying the corrosion and mechanical properties of structural materials of the core of the WWER type reactors under conditions of a loss-of-coolant accident
Description
Results of studying the fuel cans from zirconium alloy Zr 1% Nb are presented after their tests at the Parameter-M stand under conditions of the second stage of the accident with great leak. The data on the variation of the strength properties of cans in dependence on their temperature are given. The data on the effect of alloy recrystallization and grain growth on decreasing the alloy strength are presented too
Abstract (Russian)
Представлены результаты исследований оболочек твэлов из циркониевого сплава Zr 1% Nb после испытаний на стенде Параметр-М в условиях, имитирующих вторую стадию аварии с большой течью. Приведены данные по изменению прочностных характеристик оболочек в зависимости от их температуры. Представлены также данные о влиянии рекристаллизации сплава и роста зерен на уменьшение его прочностиAdditional details
Additional titles
- Original title (Russian)
- Исследование коррозионного поведения и механических свойств конструкционных материалов активной зоны реакторов типа VVEhR в условиях аварии с потерей теплоносителя
Publishing Information
- Publisher
- FGUP NII NPO Luch
- Imprint Place
- Moscow (Russian Federation)
- ISBN
- 5-87911-101-6
- Imprint Title
- Proceedings of the RSI SPA Luch. 2000-2002
- Imprint Pagination
- 252 p.
- Journal Page Range
- p. 91-99
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- Russian Federation
- INIS RN
- 36037645
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BENCHMARKS; FUEL CANS; GRAIN GROWTH; LOSS OF FLOW; MICROHARDNESS; NIOBIUM ADDITIONS; RECRYSTALLIZATION; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE 0400-1000 K; TENSILE PROPERTIES; WWER TYPE REACTORS; ZIRCONIUM BASE ALLOYS
- Descriptors DEC
- ACCIDENTS; ALLOYS; ENRICHED URANIUM REACTORS; HARDNESS; MECHANICAL PROPERTIES; NIOBIUM ALLOYS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; TEMPERATURE RANGE; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS
Optional Information
- Notes
- 10 figs., 3 tabs. Imprint:NII NPO Luch. Sbornik trudov 2000-2002 gg