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International Conference on Nuclear Engineering, Proceedings, ICONE

Volumn 4, Issue , 2008, Pages 567-577

Oxidation of advanced zirconium alloys in oxygen in the temperature range 600-1600 °C

(1) Steinbrück, Martin a

a KARLSRUHE INSTITUTE OF TECHNOLOGY (Germany)

Author keywords

[No Author keywords available]

Indexed keywords

BINARY ALLOYS; CLADDING (COATING); CORROSIVE EFFECTS; LIGHT WATER REACTORS; NIOBIUM ALLOYS; NUCLEAR ENGINEERING; NUCLEAR REACTOR ACCIDENTS; OXYGEN; THERMOOXIDATION; TIN ALLOYS; ZIRCALOY;

ACCIDENT SCENARIOS; ADVANCED ZIRCONIUM ALLOYS; EXPERIMENTAL PROGRAM; HIGH TEMPERATURE BEHAVIOR; LIGHT WATER REACTOR (LWR); OPERATIONAL CONDITIONS; OXIDATION KINETICS; WIDE TEMPERATURE RANGES;

PRESSURIZED WATER REACTORS;

EID: 70249099276 PISSN: None EISSN: None Source Type: Conference Proceeding
DOI: 10.1115/icone16-48054 Document Type: Conference Paper

Times cited : (4)

References (8)

1
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- Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys
- B. Cox, "Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys", J. Nucl. Mater. 336 (2005), 331-368.
- (2005) J. Nucl. Mater , vol.336 , pp. 331-368
- Cox, B.¹

2
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- Advanced treatment of zircaloy cladding high-temperature oxidation in severe accident code calculations. Part I. Experimental database and basic modeling
- G. Schanz, B. Adroguer, A. Volchek, "Advanced treatment of zircaloy cladding high-temperature oxidation in severe accident code calculations. Part I. Experimental database and basic modeling", Nucl. Eng. Design 232 (2004), 75-84.
- (2004) Nucl. Eng. Design , vol.232 , pp. 75-84
- Schanz, G.¹ Adroguer, B.² Volchek, A.³

3
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- Comparison of the high temperature behavior of different cladding materials
- Karlsruhe, May 22-24
- M. Grosse, "Comparison of the high temperature behavior of different cladding materials", Proceedings of the Annual Meeting on Nuclear Technology, Karlsruhe, May 22-24, 2007, 285-288.
- (2007) Proceedings of the Annual Meeting on Nuclear Technology , pp. 285-288
- Grosse, M.¹

4
- 70249091505
- Severe fuel damage experiments with advanced cladding materials to be performed in the QUENCH facility (QUENCH-ACM)
- L. Sepold, M. Grosse, M. Steinbrück, J. Stuckert, "Severe fuel damage experiments with advanced cladding materials to be performed in the QUENCH facility (QUENCH-ACM)", this conference, ICONE16-48074.
- this conference, ICONE16-48074
- Sepold, L.¹ Grosse, M.² Steinbrück, M.³ Stuckert, J.⁴

5
- 77955306763
- Single rod quench tests with Zr-lNb cladding. Comparison with Zircaloy-4
- Report FZKA-6604, Forschungszentrum Karlsruhe
- J. Stuckert, M. Steinbrück, U. Stegmaier, "Single rod quench tests with Zr-lNb cladding. Comparison with Zircaloy-4", Report FZKA-6604, Forschungszentrum Karlsruhe, 2001.
- (2001)
- Stuckert, J.¹ Steinbrück, M.² Stegmaier, U.³

6
- 70249101200
- Semi-mechanistic approach for the kinetic evaluation of experiments on the oxidation of zirconium alloys
- Report FZKA-7329, Forschungszentrum Karlsruhe
- G. Schanz, "Semi-mechanistic approach for the kinetic evaluation of experiments on the oxidation of zirconium alloys", Report FZKA-7329, Forschungszentrum Karlsruhe, 2007
- (2007)
- Schanz, G.¹

7
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- Comparison of the high temperature steam oxidation kinetics of advanced cladding materials
- June 8-12, Anaheim, CA, USA
- M. Grosse, "Comparison of the high temperature steam oxidation kinetics of advanced cladding materials", Proceedings of International Congress on Advances in Nuclear Power Plants (1CAPP '08), June 8-12, 2008, Anaheim, CA, USA.
- (2008) Proceedings of International Congress on Advances in Nuclear Power Plants (1CAPP '08)
- Grosse, M.¹

8
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- The O-Zr (Oxygen-Zirconium) System
- J.B. Abriata, J. Garces, R. Versaci, "The O-Zr (Oxygen-Zirconium) System", Bull. Alloy Phase Diagr. 7 (1986), 116-124.
- (1986) Bull. Alloy Phase Diagr , vol.7 , pp. 116-124
- Abriata, J.B.¹ Garces, J.² Versaci, R.³

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