Failure of high burnup fuels under reactivity-initiated accident conditions

Sugiyama, Tomoyuki; Umeda, Miki; Fuketa, Toyoshi; Sasajima, Hideo; Udagawa, Yutaka; Nagase, Fumihisa

doi:10.1016/j.anucene.2008.12.003

Cited by 34 publications

(18 citation statements)

References 6 publications

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“…This assumption is supported by the PIE results showing that cracks were observed in the hydride rim region even in nonfailure cases. 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.…”

Section: Introductionmentioning

confidence: 77%

“…[1][2][3][4][5]9) In the present study, directly along the assumed failure mechanism described in Sec. I, we tried to formulate the failure index with a general parameter of fracture toughness, K I .…”

Section: Pulse Irradiation Test Resultsmentioning

confidence: 99%

“…They include the recent VA-1 and VA-2 cases and other cases reported in several papers. [1][2][3][4][5]9) Figure 5 shows the maximum fuel pellet enthalpy in nonfailure cases and failure enthalpy in failure cases as functions of burnup, for the experiments listed in Tables 1 and 2. These enthalpy values are also evaluated by RANNS based on the measured failure time and the test conditions such as linear heat rate and fuel rod geometry.…”

Section: Analyzed Experimentsmentioning

confidence: 99%

“…[1][2][3][4][5]9) Here, only the test conditions and results of VA-2, the recently conducted test of a very high burnup case, are briefly described. Figure 1 shows the NSRR power history in VA-2 with the histories in other high-burnup PWR fuel experiments conducted before.…”

Section: Nsrr Pulse Irradiation Tests Of High-burnup Pwr Fuelsmentioning

confidence: 99%

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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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Section: Introductionmentioning

confidence: 77%

Section: Pulse Irradiation Test Resultsmentioning

confidence: 99%

Section: Analyzed Experimentsmentioning

confidence: 99%

Section: Nsrr Pulse Irradiation Tests Of High-burnup Pwr Fuelsmentioning

confidence: 99%

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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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“…These tests have provided knowledge about high-burnup fuel behavior and data of failure limit against the Pellet-Cladding Mechanical Interaction (PCMI) under RIA conditions. 1,2) On the basis of the NSRR experimental data as well as of the SPERT, PBF, 3) and CABRI 4) data, the Nuclear Safety Commission of Japan established the PCMI failure criteria in 1998. 5) The PCMI failure limit strongly depends on the cladding mechanical properties, which are functions of cladding hydrogen content, cladding temperature, and so on.…”

Section: Introductionmentioning

confidence: 99%

Evaluation of Initial Temperature Effect on Transient Fuel Behavior under Simulated Reactivity-Initiated Accident Conditions

Sugiyama¹,

Udagawa²,

Fuketa³

2010

Journal of Nuclear Science and Technology

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In order to evaluate possible effects of initial temperature on the transient fuel behavior, such as cladding deformation and fission gas release, under reactivity-initiated accident conditions, two comparative pulse-irradiation tests were performed on identical high-burnup PWR fuel rods under different temperature conditions at the Nuclear Safety Research Reactor (NSRR). The test RH-1 was carried out at room temperature of $20 C, while the coolant temperature in the test RH-2 was $280 C corresponding to the hot zero power temperature of PWR. The fuel rods did not fail in both tests against fuel enthalpy increases of 462 and 378 J/g, respectively. The results of the two tests were generally consistent with data previously obtained in a number of tests at room temperature, when the data were plotted as a function of the peak fuel enthalpy, not of the maximum increase in fuel enthalpy. Computer analysis using the RANNS code confirmed that the cladding residual deformation in the test RH-2 was driven only by the pellet thermal expansion and that the gas-induced deformation did not occur because the cladding temperature did not become high enough to enhance creep deformation even in the film boiling on the cladding surface.

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The Mechanical Response Evaluation of Advanced Claddings During Proposed Reactivity Initiated Accident Conditions

Cinbiz

Brown

Terrani

et al. 2017

The Minerals, Metals &Amp; Materials Series

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Failure of high burnup fuels under reactivity-initiated accident conditions

Cited by 34 publications

References 6 publications

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

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

Evaluation of Initial Temperature Effect on Transient Fuel Behavior under Simulated Reactivity-Initiated Accident Conditions

The Mechanical Response Evaluation of Advanced Claddings During Proposed Reactivity Initiated Accident Conditions

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