Hydrogen in zirconium alloys: A review

When zirconium alloys are used in water-cooled reactors, they are subjected to waterside corrosion. The emphasis of this chapter is on uniform oxidation and hydrogen embrittlement. The twin processes of oxidation and hydriding are described comprehensively in terms of their underlying mechanisms.

Corrosion of Zirconium Alloys

Hydrogen-enhanced degradation and oxide effects in zirconium alloys for nuclear applications

Stress-reorientation of hydrides and hydride embrittlement of Zr-2.5 wt% Nb pressure tube alloy

Terminal solid solubility of hydrogen in Zr-alloy pressure tube materials

Modeling of temperature dependence of stress-reorientation of hydrides in CWSR Zr-alloys (Mumbai)

Impact toughness of Zr-2.5Nb pressure tube material was evaluated as a function of specimen geometry, orientation and test temperature. Two types of samples were used. Curved impact specimens were machined directly from the tube section thereby retaining the pressure tube curvature and flat impact specimens were machined from a flattened tube section subjected to stress relieving treatment. In both the cases the specimen thickness was the actual pressure tube thickness that is 3.5 mm and the other dimension of the impact specimen was 55 mm × 10 mm. The tests were carried out for both as-received and hydrided pressure tubes between room temperature and 300 °C. As the Zr-2.5Nb pressure tube material is anisotropic, the studies were also carried out using specimens with crack growth either along axial or along transverse direction of the tube. The paper describes the results generated and discusses the materials impact toughness behaviour under different conditions.

Effect of Specimen Geometry, Orientation and Temperature on the Impact Toughness of Zr-2.5Nb Pressure Tube

-The core shrouds of twin reactors at Tarapur Atomic Power Station (TAPS) belong to the early class of Boiling Water Reactors and are in operation since 1969. With the background information of many cases of core shroud cracking in foreign countries, a technique has been developed for in-situ scooping out of material and evaluation of mechanical properties of TAPS core shrouds. This paper gives a brief history of core shroud cracking experience world over and related findings; development of scooping technique; preparation of miniature specimens from scooped material, evaluation of mechanical properties using miniature test specimens and validation. Keywords-Life management, boat sampling technique, core shroud, miniature specimen

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Development and Validation of In-Situ Boat Sampling Technique for Mechanical Property Evaluation and Life Management of TAPS Core Shroud

Water Reactor Fuel Performance Meeting – WRFPM2008 held on October 19-23, 2008 at Seoul, Republic of Korea

Influence of temperature on δ-hydride habit plane in α-Zirconium

Modeling of temperature dependence of stress-reorientation of hydrides in CWSR Zr-alloys (Seoul)

R.N. Singh

Papers

Modeling of temperature dependence of stress-reorientation of hydrides in CWSR Zr-alloys (Mumbai)

Effect of Specimen Geometry, Orientation and Temperature on the Impact Toughness of Zr-2.5Nb Pressure Tube

Development and Validation of In-Situ Boat Sampling Technique for Mechanical Property Evaluation and Life Management of TAPS Core Shroud

Influence of temperature on δ-hydride habit plane in α-Zirconium

Modeling of temperature dependence of stress-reorientation of hydrides in CWSR Zr-alloys (Seoul)