Published 1999
| Version v1
Book
The bulk of specimens and their distribution by temperature in impact bend testing
Creators
Description
In order to predict serviceability of a reactor vessel material it is proposed to make more precise the testing procedure in specimens distribution when determining the impact energy temperature dependence. The obligatory constituents of the prediction are the following: the choice of test temperature range, the quantity of specimens and their distribution by test temperatures that permits to obtain stable averaged values; the check of assumptions against experimental results. The decrease of control and initial specimens quantity results in an overestimation of conservative prediction of the WWER vessel serviceability
Additional details
Additional titles
- Original title (Russian)
- Массив образцов и распределение их по температуре при испытании на ударный изгиб
Publishing Information
- Publisher
- GNTh RF NIIAR
- Imprint Place
- Dimitrovgrad (Russian Federation)
- ISBN
- 5-85165-373-6
- Imprint Title
- Methodological provisions of reactor materials testing. Collection of the seminar abstracts
- Imprint Pagination
- 99 p.
- Journal Page Range
- p. 90-92
Conference
- Title
- Methodological provisions of reactor materials testing
- Original Conference Title
- Metodicheskoe obespechenie reaktornogo materialovedeniya
- Dates
- 30-31 Mar 1999
- Place
- Dimitrovgrad (Russian Federation)
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- Russian Federation
- INIS RN
- 30034245
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DISTRIBUTION; DUCTILE-BRITTLE TRANSITIONS; FORECASTING; IMPACT TESTS; PRESSURE VESSELS; STEELS; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE 0065-0273 K; TEMPERATURE RANGE 0273-0400 K; TRANSITION TEMPERATURE; WWER TYPE REACTORS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CONTAINERS; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS TESTING; MECHANICAL TESTS; PHYSICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; TEMPERATURE RANGE; TESTING; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 refs., 3 figs., 1 tab. Imprint:Metodicheskoe obespechenie reaktornogo materialovedeniya. Sbornik referatov seminara