Deformation conditions in the vicinity of concentrators at low-cycle stress of sizeable samples from reactor pressure vessel material
Description
Deformation conditions were investigated in a reactor pressure vessel in the vicinity of points where stress and deformation concentrate to a multi-axis stress. The cycle deformation growth in the notch root in the first cycle of low-cycle fatigue stress of a sizeable flat bar with a bore, made from the 15Kh2MFA material, with a transient force cycle may be expressed using the Neuber formula αsub(H)sup(2)=αsub(delta).αsub(epsilon) considering the deformation curve delta - epsilon. In the second and other cycles the procedure does not yield reliable predictions because it does not consider the strengthening of the plasticized area in the notch root and the formation of inner pressure stress after the first cycle. For a transient cycle of stress of a flat bar with a bore (αsub(H) is approximately 2.6) the pressure stress in the notch root can be considered to attain a level of (0.5 to 0.6).deltasub(0.2) in the second cycle and of (0.2 to 0.35).deltasub(0.2) in a half of service life. Taking into consideration the expression (deltasub(N) - deltasub(NZ)) instead of deltasub(N) in the Neuber hyperbola equation can offer more accurate prediction of cyclic deformation in the notch root and in the second and other cycles than the conventional Neuber method. The results of the study of deformation conditions in the vicinity of the bore in the flat bar can be also applied to the areas of stress concentrators in the pressure vessel and can be used for the rendition of the vessel reliability results more accurate. (B.S.)
Additional details
Additional titles
- Original title (Czech)
- Deformacni podminky v okoli koncentratoru pri nizkocyklovem zatezovani rozmernych vzorku z materialu reaktorove nadoby
Publishing Information
- Imprint Title
- Material and technological aspects of WWER reactors. II
- Imprint Pagination
- 234 p.
- Journal Page Range
- p. 412-428.
Conference
- Title
- Material and technological aspects of WWER reactors.
- Dates
- 30 Oct - 1 Nov 1978.
- Place
- Zelezna Ruda, Czechoslovakia.
INIS
- Country of Publication
- Serbia and Montenegro
- Country of Input or Organization
- Serbia and Montenegro
- INIS RN
- 13645650
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CHROMIUM-MOLYBDENUM STEELS; COPPER ADDITIONS; DEFORMATION; MANGANESE ADDITIONS; MECHANICAL TESTS; NICKEL ADDITIONS; NOTCHES; PRESSURE VESSELS; SILICON ADDITIONS; STEEL-15KH2MFA; STRAINS; STRESS ANALYSIS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CONTAINERS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS TESTING; MOLYBDENUM ALLOYS; STEELS; TESTING; TRANSITION ELEMENT ALLOYS; VANADIUM ADDITIONS
Optional Information
- Notes
- Imprint:Materialove a technologicke otazky jadernych reaktoru VVER II.