Published April 2001
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Internal Friction of Pressure Vessel Steel Embrittlement
Description
The contribution consists of an abstract of a PhD thesis. The thesis contains a literature study, a description of the construction details of a new inverted torsion pendulum. This device was designed to investigate pressure-vessel steels at high amplitudes (10-4 to 10-2) and over a wide temperature range (90-700K) at approximately 1 Hz in the irradiated condition. Results of measurements on a variety of reactor pressure vessel steels by means of the torsion penduli are reported and interpreted
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Additional details
Identifiers
Publishing Information
- Publisher
- Belgian Nuclear Research Center SCK-CEN, Mol
- Imprint Place
- Mol (Belgium)
- Imprint Title
- 2000 Scientific Report
- Imprint Pagination
- 176 p.
- Journal Page Range
- p. 164
- Report number
- INIS-BE--0003
INIS
- Country of Publication
- Belgium
- Country of Input or Organization
- Belgium
- INIS RN
- 32053193
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- BR-2 REACTOR; EMBRITTLEMENT; INTERNAL FRICTION; PRESSURE VESSELS; PROGRESS REPORT; THERMONUCLEAR REACTOR MATERIALS
- Descriptors DEC
- CONTAINERS; DOCUMENT TYPES; ENRICHED URANIUM REACTORS; FRICTION; IRRADIATION REACTORS; MATERIALS; MATERIALS TESTING REACTORS; REACTORS; TANK TYPE REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- The abstract is a contribution to the 2000 Scientific Report of the Belgian Nuclear Research Centre SCK-CEN