Neutron embrittlement of the reactor vessel in Borssele as determined from Charpy specimens
Creators
- 1. N.V. KEMA, R and D Division, Department of Reactor Physics, Arnhem (Netherlands)
- 2. N.V. KEMA, Mechanical and Chemical Testing and Consulting Division, Mechanical and Thermohydraulic Analysis and Metallurgical Research Department, Arnhem (Netherlands)
Description
Two sets of Charpy specimens have been retrieved from the reactor in the nuclear power plant at Borssele after two and four cycles of operation, respectively. The neutron fluxes at the sample positions and at the vessel wall have been calculated with a point-kernel method and S2 calculations. The calculated fluxes at the two specimen positions are in fair agreement with fluences measured by threshold detectors. The Reference Temperature of Nil Ductility has been determined from the Charpy tests by a tan-h fit procedure. An extrapolation to a 40-year vessel life has been made on the basis of a square-root dependence of the change in the reference temperature with effective full-power years. Under these assumptions the heat-affected zone material will reach 296 K. The other materials will remain below 280 K. The vessel life therefore is not limited by embrittlement. (orig.)
Additional details
Publishing Information
- Publisher
- KEMA.
- Imprint Place
- Arnhem (Netherlands)
- ISBN
- 90-353-0008-4
- Imprint Pagination
- p. 45-54.
- Journal Volume
- 1
- Journal Issue
- 4
- Series
- Kema Sci. Tech. Rep.
- ISSN
- 0167-8590
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 15068106
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- BORSSELE REACTOR; CHARPY TEST; CORROSION; EMBRITTLEMENT; EXPERIMENTAL DATA; NEUTRON FLUX; REACTOR VESSELS
- Descriptors DEC
- CHEMICAL REACTIONS; CONTAINERS; DATA; DESTRUCTIVE TESTING; ENRICHED URANIUM REACTORS; IMPACT TESTS; INFORMATION; MATERIALS TESTING; MECHANICAL TESTS; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; RADIATION FLUX; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 18 figs.; 3 tables.