Published 1990 | Version v1
Book

The lifespan of nuclear reactor pressure vessels

Creators

  • 1. TRACTEBEL, Brussels (Belgium)

Description

The main degradation mechanisms of a PWR reactor pressure vessel is irradiation embrittlement. The limiting criterion will be either the RTNDT of the inside surface of the vessel, submitted to the maximum neutron flux, or the decrease in upper shelf energy level (mainly for older US plants). For older pressure vessels, this embrittlement could reduce the life of the vessel, and when a high embrittlement is expected, a flux reduction program implemented soon enough could be an effective mitigating measure. When no other solution is available, an anneal of the pressure vessel seems to be feasible and would allow to restore partially its properties. (author) 8 figs., 1 tab., 13 refs

Additional details

Additional titles

Original title (no language)
SVA-Vertiefungskurs: Leistungserhoehung und Lebensdauer-Verlaengerung von Kernkraftwerken.

Publishing Information

Publisher
Schweizerische Vereinigung fuer Atomenergie (SVA).
Imprint Place
Bern (Switzerland)
Imprint Title
SVA further education course: power upgrading and lifespan expansion of nuclear power plants
Imprint Pagination
vp.
Journal Page Range
p. C-2.1-C-2.15.

Conference

Title
power upgrading and lifespan expansion of nuclear power plants.
Original Conference Title
SVA-Vertiefungskurs: Leistungserhoehung und Lebensdauer-Verlaengerung von Kernkraftwerken
Acronym
SVA further education course
Dates
25-27 Apr 1990.
Place
Brugg-Windisch (Switzerland).

INIS

Country of Publication
Switzerland
Country of Input or Organization
Switzerland
INIS RN
23067921
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
ANNEALING; CHARPY TEST; CRACK PROPAGATION; EMBRITTLEMENT; EXPERIMENTAL DATA; LIFETIME; MONITORING; NEUTRON FLUX; PRESSURE VESSELS; STRAIN AGING; THERMAL SHOCK
Descriptors DEC
AGING; CONTAINERS; DATA; DESTRUCTIVE TESTING; HEAT TREATMENTS; IMPACT TESTS; INFORMATION; MATERIALS TESTING; MECHANICAL TESTS; NUMERICAL DATA; RADIATION FLUX; TESTING

Optional Information

Notes
Imprint:SVA-Vertiefungskurs: Leistungserhoehung und Lebensdauer-Verlaengerung von Kernkraftwerken.