The influence of hydrogen on oxygen distribution inside Zry-4 fuel cladding
Source abstract
Abstract
Abstract This study is concerned with oxygen concentration measurements inside the Zry-4 fuel cladding wall after high-temperature oxidation. The oxygen distribution has been determined using the WDS method and also by nanohardness measurement. The relationship between the nanohardness and the oxygen concentration at the α/β phase boundary in the α-Zr(O) region has been explored. The hydrogen influence on the oxygen distribution was examined. The results were compared with results of other authors, showing satisfactory agreement. It was concluded that the oxygen concentration measurement inside the cladding wall after the isothermal high-temperature oxidation could be used for constructing the Zr-alloy–Oxygen phase diagram.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Fusion materials and technologies
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References (17)
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1. Atomic Energy Commission Rule-Making Hearing, Opinion of the Commission, Docket RM-50-1, December 28, 1973.
2. Chung · Nucl. Eng. Technol. · 2005 · 37 · 327
3. Portier · J. ASTM Int. · 2005 · 2 · 10310.1520/JAI12468 ↗
4. M.C. Billone, LOCA Embrittlement Correlation, Argonne National Laboratory Interim Report, April 8, 2005.
5. V. Vrtilkova, L. Novotny, R. Doucha, J. Vesely, An approach to the alternative LOCA embrittlement criterion, in: Proceedings of Meeting of OECD Nuclear Energy Agency Committee on the Safety of Nuclear Installations Special Expert Group on Fuel Safety Margins (SEGFSM), May 25–26, 2004, Argonne, Illinois, USA.
6. H.M. Chung, T.F. Kassner, Embrittlement Criteria for Zircaloy Fuel Cladding Applicable to Accident Situations in Light-Water Reactors, NUREG/CR-1344, ANL-79-48, Argonne National Laboratory, January 1980.10.2172/5496633 ↗
7. Zuzek · Bull. Alloy Phase Diagr. · 1990 · 11 · 38510.1007/BF02843318 ↗
8. Coleman · J. Less-Common Met. · 1966 · 11 · 16810.1016/0022-5088(66)90003-8 ↗
9. Hsu · J. Alloys Compd. · 2006 · 426 · 25610.1016/j.jallcom.2005.12.113 ↗
10. V. Vrtilkova, Termomechanické vlastnosti povlakové trubky ze Zr-slitin po vysokoteplotních přechodech, UJP PRAHA a.s. Research Report, December 15, 2008, in Czech.
11. J.C. Brachet, L. Portier, et al., Influence of Hydrogen Content on the α–β phase Transformation Temperatures and on the Thermal–Mechanical Behavior of Zry-4, M4 and M5™ Alloys During the First Phase of LOCA Transient, Zirconium in the Nuclear Industry: Thirteenth International Symposium. Annecy, STP 1423, 2001, pp. 673–701.10.1520/STP11411S ↗
12. Ma · J. Nucl. Mater. · 2008 · 377 · 35910.1016/j.jnucmat.2008.03.012 ↗
13. Chung · J. Nucl. Mater. · 1979 · 84 · 32710.1016/0022-3115(79)90172-7 ↗
14. Stern · J. ASTM Int. · 2007 · 4 · 110.1520/JAI100908 ↗
15. M. Négyesi, Influence of hydrogen concentration in alloys on mechanical properties of Zr-alloy used as fuel cladding after LOCA transient, CTU FNSPE DM Bachelor Thesis, July 4, 2007 (in Czech).
16. Abriata · Bull. Alloy Phase Diagr. · 1986 · 7 · 11610.1007/BF02881546 ↗
17. M. Négyesi, Influence of hydrogen concentration in alloys on oxygen distribution in Zr-alloy used as fuel cladding after LOCA transient, CTU FNSPE DM Research Report, June 19, 2008 (in Czech).