Study of clad ballooning and rupture behavior of fuel pins of Indian PHWR under simulated LOCA condition

Sawarn, Tapan K.; Banerjee, Suparna; Pandit, K.M.; Anantharaman, S.

doi:10.1016/j.nucengdes.2014.10.011

Cited by 17 publications

(4 citation statements)

References 8 publications

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“…A comprehensive set of ballooning-burst experiments for Indian PHWR, is discussed by Sawarn et al 2014, andSawarn et al 2017. The database may not be directly applicable to LWR conditions because of lower clad thickness, lower burn-up and lower internal pressure.…”

Section: Ballooning and Burstmentioning

confidence: 99%

The technological challenge for current generation nuclear reactors

D'Auria¹,

Debrecin²,

Glaeser³

2019

NUCET

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The present paper deals with the proposal of an additional safety barrier for the class of large (1000 MWe or more) Light Water Reactors (LWR) now in operation, in construction, or under design. Emphasis is given to the motivations or the needs for the barrier. Two main parts of the paper can be distinguished. The following topics are discussed in the former part (section 2): (a) the weakness of the barrier constituted by the current design of nuclear fuel; (b) the continuously increasing complexity of the system, with main reference to the Instrumentation and Control (I&C); (c) the role that the Large Break Loss of Coolant Accident (LBLOCA) had for arriving at the current layout of the Reactor Coolant System (RCS). Furthermore avoiding the severe accidents in 1979, 1987 and 2011, is at the basis of the proposal. In the latter part (sections 3 and 4), the elements of the proposed technological safety barrier are discussed: the As-Low-As-Reasonably-Achievable (ALARA) principle, the Best Estimate Plus Uncertainty (BEPU) approach, the Extended Safety Margin Detection (E-SMD) hardware, the Emergency Rescue Team (ERT) strategy (or a virtual entity for the reactor) and the Independent Assessment (IA) concept. The additional safety barrier, although not demonstrated in the paper, is expected to reduce for a factor in the range 10–1000 the probability of core melt and to have a cost in the order of 1% the cost of a nuclear reactor unit.

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Section: Ballooning and Burstmentioning

confidence: 99%

The technological challenge for current generation nuclear reactors

D'Auria¹,

Debrecin²,

Glaeser³

2019

NUCET

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“…Over the last decade, researchers have developed a range of experimental approaches that include specimen observation and in-situ measurements as part of the experiment design [7][8][9]. Regarding the cladding tube specimen, in-situ analysis allows for creep rate evaluation and estimation of true stress in…”

Section: Path Forwardmentioning

confidence: 99%

Execution of Targeted Experiments to Inform BISON for ATF Materials: An Advanced Approach to Tube Burst Testing

Gussev

Howell

Terrani

et al. 2019

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This report describes a new, advanced experimental approach for testing tube specimens loaded by internal pressure. The approach allows conventional tube burst testing to be performed and employs digital image recording and analysis for conducting noncontact optic strain measurements. Section 1 provides a brief introduction and motivation for the project. Section 2 describes the selected approach and provides technical details regarding the modified experimental tube burst system: a commercial infrared furnace redesigned to support this work by adding two 50-mm-diameter optic ports to make the specimen visible during the burst tests, and a digital camera used to record specimen images, lens, and optic filters.Section 3 briefly analyzes a typical burst test and the digital image correlation dataset, recorded during the experiment, and discusses the experiment outcome, including local strains along the tube specimen. Additionally, Section 3 focuses on the issues influencing the in situ strain measurement accuracy and final results and suggests changes in the experimental scheme to improve data quality and reliability. The conclusion summarizes the work performed to date and discusses the possible future activity.

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“…If the fuel cladding is not firm and tenacious enough, the nuclear fuel rod may crack easily, causing the radioactive material to break through the cladding and leak, resulting in severe consequences. Subsequently, accident tolerant fuel and cladding materials under LOCA conditions are studied by many researchers (Isobe and Suda, 1999;Forgeron et al, 2000a;Sawarn et al, 2014;Park et al, 2016;Suman et al, 2016;Gamble et al, 2017;Tang et al, 2017;Jailin et al, 2020), especially after the event at Fukushima Daiichi Nuclear Power Plant.…”

Section: Introductionmentioning

confidence: 99%

Coupled Modeling and Simulation of Phase Transformation in Zircaloy-4 Fuel Cladding Under Loss-of-Coolant Accident Conditions

Lu¹,

Qian

Zhou

2021

Front. Energy Res.

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Under loss-of-coolant conditions, the temperature on fuel cladding will increase rapidly (up to 1000–1500 K), which will not only cause a dramatic oxidation reaction of Zircaloy-4 and an increase in hydrogen concentration but also cause an allotropic phase transformation of Zircaloy-4 from hexagonal (α-pahse) to cubic (β-phase) crystal structure. As we all know, thermophysical properties have a close relationship with the microstructure of the material. Moreover, because of an important influence of the phase transformation on the creep resistance and the ductility of the fuel rod, studying the crystallographic phase transformation kinetics is pivotal for evaluating properties for fuel rod completeness. We coupled the phase transformation model together with the existing physical models for reactor fuel, gap, cladding, and coolant, based on the finite element analysis and simulation software COMSOL Multiphysics. The critical parameter for this transformation is the evolution of the volume fraction of the favored phase described by a function of time and temperature. Hence, we choose two different volume fractions (0 and 10%) of BeO for UO2-BeO enhanced thermal conductivity nuclear fuel and zircaloy cladding as objects of this study. In order to simulate loss-of-coolant accident conditions, five relevant parameters are studied, including the gap size between fuel and cladding, the temperature at the extremities of the fuel element, the coefficient of heat transfer, the linear power rate, and the coolant temperature, to see their influence on the behavior of phase transformation under non-isothermal conditions. The results show that the addition of 10vol%BeO in the UO2 fuel decreased the phase transformation effect a lot, and no significant phase transformation was observed in Zircaloy-4 cladding with UO2-BeO enhanced thermal conductivity nuclear fuel during existing loss-of-coolant accident conditions.

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Study of clad ballooning and rupture behavior of fuel pins of Indian PHWR under simulated LOCA condition

Cited by 17 publications

References 8 publications

The technological challenge for current generation nuclear reactors

The technological challenge for current generation nuclear reactors

Execution of Targeted Experiments to Inform BISON for ATF Materials: An Advanced Approach to Tube Burst Testing

Coupled Modeling and Simulation of Phase Transformation in Zircaloy-4 Fuel Cladding Under Loss-of-Coolant Accident Conditions

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