Published October 2014 | Version v1
Miscellaneous

The Prediction of Creep behaviors of Zircaloy-4 Using Uniaxial Stress Relaxation

  • 1. Hanyang Univ., Seoul (Korea, Republic of)
  • 2. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

Zirconium alloys have been used as a reactor component material because of their favorable neutronic properties, good mechanical behavior at elevated temperature and high corrosion resistance. In reactor operation condition, creep is one of the significant degradation mechanisms in zirconium alloys. Recently, creep is known as a critical factor which threatens the integrity of cladding with hydride reorientation in dry storage condition. However, the evaluation of creep is not easy, because creep test requires a considerable time. It is known that stress relaxation and creep are correlated analytically. Creep behavior can be derived from stress relaxation test with a relatively short time. In this paper, creep behavior of Zircaloy-4 is predicted using uniaxial stress relaxation. Creep behaviors of Zry-4 were predicted using stress relaxation. The stress relaxation test was conducted under tensile stresses of 65-187MPa at 400 .deg. C. The stress relaxation results were analytically converted to the predicted creep curves. The saturated primary creep strains (εsat) were 0.029 mm/mm at 100MPa and 0.033 mm/mm at 120 MPa. The steady state creep rates (aess) were 2.48*10-8s-1 at 100 MPa and 2.22*10-7s-1 at 120 MPa. The predicted creep behavior for 100 MPa coincided well with the experimental data but that for 120 MPa was not

Part of:
Proceedings of the KNS 2014 Fall Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2014 Fall Meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2014 Fall Meeting of the KNS
Dates
29-31 Oct 2014
Place
Pyongchang (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
46060677
Subject category
S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference, Numerical Data, Non-conventional Literature
Descriptors DEI
CLADDING; CREEP; EXPERIMENTAL DATA; FORECASTING; REACTOR COMPONENTS; RELAXATION; STRESSES; ZIRCALOY 4
Descriptors DEC
ALLOYS; ALLOY-ZR98SN-4; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DATA; DEPOSITION; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; INFORMATION; IRON ADDITIONS; IRON ALLOYS; MATERIALS; MECHANICAL PROPERTIES; NUMERICAL DATA; SURFACE COATING; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS

Optional Information

Notes
6 refs, 6 figs, 1 tab