Influence of hydrogen concentration on burst parameters of Zircaloy-4 cladding tube under simulated loss-of-coolant accident
Description
Single-tube burst tests on hydrogenated Zircaloy-4 nuclear fuel cladding under simulated loss-of-coolant accident are conducted to evaluate the impact of hydrogen on burst parameters. The heating rate and initial pressure are varied from 5 K/s to 150 K/s and 5 bar–80 bar, respectively. The hydrogen concentration in the cladding is in the range of 0–2000 wppm. Burst stress is lower for hydrogenated cladding in α-phase. A significant loss of ductility is observed in α-phase and lower α + β-phase for hydrogenated cladding. However, the burst strain is higher for hydrogenated cladding in β-phase. There is a sigmoidal dependency of rupture area with initial stress and rupture area is larger for hydrogenated cladding. A novel burst stress correlation for hydrogenated Zircaloy-4 cladding has been proposed
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Technology
- Journal Volume
- 52
- Journal Issue
- 9
- Series
- 21 refs, 9 figs, 3 tabs
- Journal Page Range
- p. 2047-2053
- ISSN
- 1738-5733
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 52113454
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- CLADDING; CONCENTRATION RATIO; DUCTILITY; HEATING RATE; HYDROGEN; HYDROGENATION; LOSS OF COOLANT; NUCLEAR FUELS; RUPTURES; STRAINS; STRESSES; TUBES; ZIRCALOY 4
- Descriptors DEC
- ACCIDENTS; ALLOYS; ALLOY-ZR98SN-4; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DEPOSITION; DIMENSIONLESS NUMBERS; ELEMENTS; ENERGY SOURCES; FAILURES; FUELS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; IRON ADDITIONS; IRON ALLOYS; MATERIALS; MECHANICAL PROPERTIES; NONMETALS; REACTOR ACCIDENTS; REACTOR MATERIALS; SURFACE COATING; TENSILE PROPERTIES; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS