Published December 1988 | Version v1
Miscellaneous

Fracture mechanics parameters of WWER-1000 reactor pressure vessel materials

  • 1. Skoda, Plzen (Czechoslovakia). Zavod Energeticke Strojirenstvi

Description

The results are summed up of evaluating the tests of fracture toughness and crack propagation rate by repeated stress at a constant amplitude of base material loading. Steels 15Kh2NMFA and 15Kh2NMFAA were used designed for WWER-1000 reactor pressure vessels. The regression and the bottom envelope curves of fracture toughness were also determined for steel 15Kh2MFA for WWER-440 reactor pressure vessels; they were compared with the reference curve using the MKhO IAE Standard and analyzed with respect to the effect of the test body thickness. The crack propagation rate expressed in dependence on the stress intensity coefficient sweep is compared with calculated curves listed in the Soviet and in the US literature. (author). 2 figs., 7 refs

Part of:
Material and technology problems of WWER nuclear reactors

Additional details

Additional titles

Original title (Czech)
Parametry lomove mechaniky materialu TN reaktoru VVER 1000

Publishing Information

Imprint Title
Material and technology problems of WWER nuclear reactors
Imprint Pagination
258 p.
Journal Page Range
p. 141-147.
Report number
INIS-mf--11567

Conference

Title
3. conference on material and technology problems of WWER nuclear reactors.
Original Conference Title
III. konference ''Materialove a technologicke otazky jadernych reaktoru VVER''
Dates
5-8 Dec 1988.
Place
Srni (Czechoslovakia).

Optional Information

Notes
Imprint:Materialove a technologicke otazky jadernych reaktoru VVER.;III. konference.