Published April 1997
| Version v1
Report
Restricted
The primary circuit materials properties results analysis performed on archive material used in NPP V-1 and Kola NPP Units 1 and 2
Description
A very brief summary is provided of a primary circuit piping material properties analysis. The analysis was performed for the Bohunice V-1 reactor and the Kola-1 and -2 reactors. Assessment was performed on Bohunice V-1 archive materials and primary piping material cut from the Kola units after 100,000 hours of operation. Main research program tasks included analysis of mechanical properties, corrosion stability, and microstructural properties. Analysis results are not provided
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Title
- Proceedings of the seminar on leak before break in reactor piping and vessels
- Imprint Pagination
- 773 p.
- Journal Page Range
- p. 154.
- Report number
- NUREG/CP--0155
Conference
- Title
- Seminar on leak before break in reactor piping and vessels.
- Dates
- 9-11 Oct 1995.
- Place
- Lyon (France).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28076027
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOHUNICE V-1 REACTOR; KOLA-1 REACTOR; KOLA-2 REACTOR; MATERIALS TESTING; PIPES; PRIMARY COOLANT CIRCUITS
- Descriptors DEC
- COOLING SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Secondary number(s)
- CONF-9510432--.