Influence of Precipitated Hydride on the Fracture Behavior of Zircaloy Fuel Cladding Tube

Kuroda, Masatoshi; Yoshioka, K; Yamanaka, Shinşuke; Anada, Hiroyuki; Nagase, Fumihisa; Uetsuka, Hiroshi

doi:10.1080/18811248.2000.9714942

Cited by 32 publications

(7 citation statements)

References 8 publications

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“…Through-thickness crack propagation and fracture toughness of hydrided zirconium alloys was previously analyzed at 25°C, 300°C, 375°C by Dubey et al (1999), Kuroda et al (2000), Pierron et al (2003), Glendening et al (2004), Desquines et al (2005), Bertolino et al (2006), Tomiyasu et al (2007), Daum et al (2007), Georgenthum et al (2008), Udagawa et al (2009), Sartoris et al (2010, Hsu et al (2011), Raynaud et al (2012. It appears in these studies that hydrogen content and hydride orientation are key parameters to assess zirconium alloys fracture toughness at room temperature.…”

Section: Introductionmentioning

confidence: 97%

Fracture of Zircaloy-4 Fuel Cladding Tubes with Hydride Blisters

Macdonald¹,

Boulch²,

Ménibus³

et al. 2014

Procedia Materials Science

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The influence of hydride blister on cold worked stress relieved Zircaloy-4 cladding tubes fracture toughness at room temperature was studied using hoop tensile tests and plane strain tensile tests. The experimental macroscopic fracture stress and strain values and an elastic-plastic finite element analysis of the mechanical tests with the CAST3M code were used to calculate the J-integral and estimate the fracture toughness for several blister depths from 120 to 240 μm.

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Section: Introductionmentioning

confidence: 97%

Fracture of Zircaloy-4 Fuel Cladding Tubes with Hydride Blisters

Macdonald¹,

Boulch²,

Ménibus³

et al. 2014

Procedia Materials Science

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“…4,5) The experiments by Kuroda et al also support this assumption: the failure stress of hydride was evaluated to be only about 18 MPa. 6) In addition, Tomiyasu et al conducted RIA simulation experiments at the NSRR with unirradiated prehydrided cladding and successfully reproduced PCMI failure as were observed in high-burnup fuels. These experiments have clearly demonstrated that hydride clusters play the most important role in PCMI failure during an RIA.…”

Section: Introductionmentioning

confidence: 78%

Stress Intensity Factor at the Tip of Cladding Incipient Crack in RIA-Simulating Experiments for High-Burnup PWR Fuels

Udagawa

Suzuki

Sugiyama

et al. 2009

Journal of Nuclear Science and Technology

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RIA-simulating experiments for high-burnup PWR fuels have been performed in the NSRR, and the stress intensity factor K I at the tip of cladding incipient crack has been evaluated in order to investigate its validity as a PCMI failure threshold under RIA conditions. An incipient crack depth was determined by observation of metallographs. The maximum hydride-rim thickness in the cladding of the test fuel rod was regarded as the incipient crack depth in each test case. Hoop stress in the cladding periphery during the pulse power transient was calculated by the RANNS code. K I was calculated based on crack depth and hoop stress. According to the RANNS calculation, PCMI failure cases can be divided into two groups: failure in the elastic phase and failure in the plastic phase. In the former case, elastic deformation was predominant around the incipient crack at failure time. K I is available only in this case. In the latter, plastic deformation was predominant around the incipient crack at failure time. Failure in the elastic phase never occurred when K I was less than 17 MPa m 1=2 . For failure in the plastic phase, the plastic hoop strain of the cladding periphery at failure time clearly showed a tendency to decrease with incipient crack depth. The combination of K I , for failure in the elastic phase, and plastic hoop strain at failure, for failure in the plastic phase, can be an effective index of PCMI failure under RIA conditions.

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“…The effect of local hydride precipitation on the mechanical properties of the matrix has attracted attention [ 147 ]. Mechanical tests, such as the Expansion Due to Compression test, and tensile tests were conducted on samples containing localized hydride and demonstrated that hydride blisters and hydride rims have no deformation capacity, even at 480 °C [ 148 , 149 , 150 , 151 , 152 ]. Notably, the reduction in the strength and plasticity of the matrix is proportional to the depth of the bister/rim.…”

Section: Hydride-induced Embrittlementmentioning

confidence: 99%

Mechanisms of Hydride Nucleation, Growth, Reorientation, and Embrittlement in Zirconium: A Review

Jia

Han

2023

Materials

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Zirconium (Zr) hydrides threaten the reliability of fuel assembly and have repeatedly induced failures in cladding tubes and pressure vessels. Thus, they attract a broad range of research interests. For example, delayed hydride cracking induced a severe fracture and failure in a Zircaloy-2 pressure tube in 1983, causing the emergency shutdown of the Pickering nuclear reactor. Hydride has high hardness and very low toughness, and it tends to aggregate toward cooler or tensile regions, which initiates localized hydride precipitation and results in delayed hydride cracking. Notably, hydride reorientation under tensile stress substantially decreases the fracture toughness and increases the ductile-to-brittle transition temperature of Zr alloys, which reduces the safety of the long-term storage of spent nuclear fuel. Therefore, improving our knowledge of Zr hydrides is useful for effectively controlling hydride embrittlement in fuel assembly. The aim of this review is to reorganize the mechanisms of hydride nucleation and growth behaviors, hydride reorientation under external stress, and hydride-induced embrittlement. We revisit important examples of progress of research in this field and emphasize the key future aspects of research on Zr hydrides.

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Influence of Precipitated Hydride on the Fracture Behavior of Zircaloy Fuel Cladding Tube

Cited by 32 publications

References 8 publications

Fracture of Zircaloy-4 Fuel Cladding Tubes with Hydride Blisters

Fracture of Zircaloy-4 Fuel Cladding Tubes with Hydride Blisters

Stress Intensity Factor at the Tip of Cladding Incipient Crack in RIA-Simulating Experiments for High-Burnup PWR Fuels

Mechanisms of Hydride Nucleation, Growth, Reorientation, and Embrittlement in Zirconium: A Review

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