Risk-informed analysis of the large break loss of coolant accident and PCT margin evaluation with the RISMC methodology

Liang, Tian; Liang, K.S.; Cheng, Chia-Ming; Pei, Bau-Shei; Patelli, Edoardo

doi:10.1016/j.nucengdes.2016.08.035

Cited by 5 publications

(3 citation statements)

References 10 publications

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“…In order to estimate f(L), g(C), and Pr[L > C] and at the same time reduce the level of subjectivity and simplifications connected to the classical use of the PRA, the RISA Pathway is developing new software tools [e.g., RAVEN 58,59 allowing the safety analyst to perform integrated deterministic PRA analyses.…”

Section: Risk-informed Safety Analysis For Accident Tolerant Fuels • mentioning

confidence: 99%

Risk-Informed Safety Analysis for Accident Tolerant Fuels

Parisi

Mandelli

et al. 2020

Nuclear Science and Engineering

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Accident tolerant fuels (ATFs) are being tested by different nuclear vendors and research organizations, and their introduction into the U.S light water reactor fleet is planned for the second half of the 2020s. Under the framework of the U.S. Department of Energy Light Water Reactor Sustainability (LWRS) Program, as part of the LWRS Risk-Informed Systems Analysis Pathway, research is being conducted at the Idaho National Laboratory (INL) to develop tools and methods that can help the industry to quantify the benefits from adopting ATF technology. In this paper we describe the developed risk-informed methodology including the safety analysis code improvements, and we present some results for selected accident scenarios. The developed methodology combines the INL state-of-the-art deterministic Best Estimate code RELAP5-3D and the probabilistic risk analysis tools RAVEN and SAPHIRE. The analyses are performed on a three-loop pressurized water reactor, simulating station blackout and large-break loss-of-coolant accidents and considering near-term ATFs or iron-chromium-aluminum and chromium-coated clads. Finally, we show how, applying our methodology, the new core damage frequency (CDF) can be assessed. The results indicate that the main benefit in introducing near-term ATFs is a significant reduction in hydrogen production during accident conditions. No significant CDF reduction was found.

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Section: Risk-informed Safety Analysis For Accident Tolerant Fuels • mentioning

confidence: 99%

Risk-Informed Safety Analysis for Accident Tolerant Fuels

Parisi

Mandelli

et al. 2020

Nuclear Science and Engineering

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“…Currently, the working environment temperature of light water reactor (LWR) is about 250 to 700 • C [7][8][9]11]; the LBE in nuclear coolant pipe is about 250 to 500 • C [12,13]. The Large-Break Loss-of-Coolant Accident (LBLOCA) is considered the worst scenario of nuclear power failure, the temperature could rise to 1200 • C when this accident happened and make the cladding wall fatigue failure [14][15][16]. Due to the high temperature condition of nuclear power plant, the consideration for thermal stress measurement and corrosion testing is necessary [17][18][19][20].…”

Section: Introductionmentioning

confidence: 99%

Corrosion Enhancement for FGM Coolant Pipes Subjected to High-Temperature and Hydrostatic Pressure

Lo¹,

Lai²

2022

Coatings

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The objective of this paper is to enhance the corrosion resistance of coolant pipes in high temperature and lateral hydrostatic pressure in critical engineering environment, especially for circular coolant pipes under hydrostatic pressure of LBE (lead-bismuth eutectic) applications in nuclear power plants. The resistance against corrosion caused by LBE liquid is mainly formed by Fe-12Cr-2Si solid solutions coatings on the pipe. The silicon concentration in Fe-12Cr-2Si can interact with LBE as an effective oxidized compound such as SiO2 and Fe2SiO4 when the silicon concentration is higher than 1.25 wt.%. The oxide film formed on the coating can resist the LBE corroding in the Fe-12Cr-2Si structure. The primary material of a constructing coolant pipe is T91 ferritic-martensitic alloys, and the surface anti-corrosion coating is Fe-12Cr-2Si solid solution. With a high strength structure, FGC (functionally graded composite material), ensures that the pipe resists the corrosion from LBE liquid. In this study, both the steady-state stress values and silicon concentration are evaluated at 700, 1000, and 1200 °C to know the fatigue problems. The research result indicates the FGM (functionally graded material) structure performs better in promoting the margin of safety on stress distribution and reserving the silicon concentration on the inner surface higher than 1.25 wt.% over 60 years as compared to the FGC structure with 34 μm thickness of Fe-12Cr-2Si coating in a high temperature environment.

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“…Since improper use of nuclear energy may cause mass destruction, it is necessary to evaluate nuclear safeguards and limit the development of nuclear detonations. Nuclear safeguards evaluations [9][10][11][12][13][14] are invoked to test and verify that states meet with the international treaty, which put forward by International Atomic Energy Agency (IAEA) and make sure that those nuclear materials will not be used to manufacture nuclear weapons. In order to make the evaluation of indicators and then make the final assessment of the States' declarations to the institution concerning any activity which are related to nuclear power, the IAEA experts collect relevant information from some main sources: information provided by the State itself, Internet and newspapers, and nonsafeguards IAEA databases.…”

Section: Introductionmentioning

confidence: 99%

An evidential evaluation of nuclear safeguards

Gao

Deng

2019

International Journal of Distributed Sensor Networks

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Nuclear safeguards evaluation is a complicated issue with many missing values and uncertainties. By invoking Dempster-Shafer theory of evidence, the missing values are assigned to a subset of a set of multiple objects, at the same time, by combining different evaluation values, and the effect of uncertainty will be decreased. In this way, both the missing values and uncertainties are considered in the final evaluations. This method has been used in considering the International Atomic Energy Agency experts' evaluation for nuclear safeguards. The result shows that (s 2 , 0.1897) is the biggest belief degree.

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Risk-informed analysis of the large break loss of coolant accident and PCT margin evaluation with the RISMC methodology

Cited by 5 publications

References 10 publications

Risk-Informed Safety Analysis for Accident Tolerant Fuels

Risk-Informed Safety Analysis for Accident Tolerant Fuels

Corrosion Enhancement for FGM Coolant Pipes Subjected to High-Temperature and Hydrostatic Pressure

An evidential evaluation of nuclear safeguards

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