Improvement and evaluation of debris coolability analysis module in severe accident analysis code SAMPSON using LIVE experiment
Sign Up to like & getrecommendations! Published in 2017 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2016.10.011
Abstract: Abstract The purpose of this work is to validate the debris coolability analysis (DCA) module in the severe accident analysis code SAMPSON by simulating the first steady stage of the LIVE-L4 test. The DCA module… read more here.
Keywords: code; module; analysis; debris coolability ... See more keywords
An improved simplified method of evaluating severe accident source term in the containment of AP1000
Sign Up to like & getrecommendations! Published in 2018 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2017.10.001
Abstract: Abstract This paper focuses on the source term estimation in AP1000 Nuclear Power Plant (NPP) under severe accident condition. Methods that utilize MELCOR code can evaluate the source term, but the evaluation process is time-consuming.… read more here.
Keywords: nureg 1465; source; severe accident; source term ... See more keywords
Analysis of loss of cooling and loss of coolant severe accident scenarios in VVER-1000/V446 spent fuel pool
Sign Up to like & getrecommendations! Published in 2020 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2019.107205
Abstract: Abstract The spent fuel storage system is designed to store and cool the spent fuel within several years with account for scheduled refueling and emergency unloading of the entire reactor core. The Fukushima nuclear disaster… read more here.
Keywords: severe accident; loss; fuel pool; spent fuel ... See more keywords
Modelling nuclear fuel behaviour with TAF-ID: Calculations on the VERDON-1 experiment, representative of a nuclear severe accident
Sign Up to like & getrecommendations! Published in 2019 at "Journal of Nuclear Materials"
DOI: 10.1016/j.jnucmat.2019.05.027
Abstract: Abstract The chemical behaviour of the main elements present in a PWR irradiated fuel sample (UO2 fuel, Zr from the Zircaloy-cladding, Pu, Np, and fission products such as Ba, Ce, Cs, Gd, I, La, Mo,… read more here.
Keywords: taf calculations; fuel; severe accident; nuclear severe ... See more keywords
Bayesian Optimization Analysis of Containment-Venting Operation in a Boiling Water Reactor Severe Accident
Sign Up to like & getrecommendations! Published in 2017 at "Nuclear Engineering and Technology"
DOI: 10.1016/j.net.2016.12.011
Abstract: Abstract Containment venting is one of several essential measures to protect the integrity of the final barrier of a nuclear reactor during severe accidents, by which the uncontrollable release of fission products can be avoided.… read more here.
Keywords: containment venting; bayesian optimization; optimization; severe accident ... See more keywords
Survivability assessment of Viton in safety-related equipment under simulated severe accident environments
Sign Up to like & getrecommendations! Published in 2018 at "Nuclear Engineering and Technology"
DOI: 10.1016/j.net.2018.02.009
Abstract: Abstract To evaluate equipment survivability of the polymer Viton, used in sealing materials, the effects of its thermal degradation were investigated in severe accident (SA) environment in a nuclear power plant. Viton specimens were prepared and… read more here.
Keywords: viton; safety related; equipment; survivability ... See more keywords
Advances in the understanding of molybdenum effect on iodine and caesium reactivity in condensed phase in the primary circuit in nuclear severe accident conditions
Sign Up to like & getrecommendations! Published in 2020 at "Nuclear Engineering and Technology"
DOI: 10.1016/j.net.2020.01.029
Abstract: Abstract In the case of a severe accident in a Light Water Reactor, the issue of late release of fission products, from the primary circuit surfaces is of particular concern due to the direct impact… read more here.
Keywords: primary circuit; iodine; severe accident; effect ... See more keywords
Quantitative assessment of severe accident management strategies in a nuclear power plant
Sign Up to like & getrecommendations! Published in 2018 at "Journal of Nuclear Science and Technology"
DOI: 10.1080/00223131.2018.1428123
Abstract: ABSTRACT Nuclear power plants in Korea are preparing improvement countermeasures for severe accidents including mobile gas turbine generators, passive autocatalytic recombiners, containment-filtered venting systems, and external injection using portable pumps. However, these improvement countermeasures have… read more here.
Keywords: nuclear power; improvement countermeasures; power; assessment ... See more keywords
Evaluation of the containment vessel failure time from operator’s notifications during a severe accident
Sign Up to like & getrecommendations! Published in 2019 at "Journal of Nuclear Science and Technology"
DOI: 10.1080/00223131.2019.1612793
Abstract: ABSTRACT This paper aims at clarifying the potential and the limit of the method to surmise the timing of the containment vessel (CV) failure utilizing the Emergency Action Levels (EALs) issued as a nuclear operator’s… read more here.
Keywords: vessel failure; time; containment vessel; failure ... See more keywords
Degradation mechanism of stainless steel by U-Zr-O molten mixture during core degradation of BWR severe accident
Sign Up to like & getrecommendations! Published in 2021 at "Journal of Nuclear Science and Technology"
DOI: 10.1080/00223131.2020.1858989
Abstract: ABSTRACT Degradation mechanism involving the interaction between the U-Zr-O phase from molten fuel cladding and steel was investigated at the lower structure of core region of the boiling water reactor, which could take place at… read more here.
Keywords: degradation; steel; degradation mechanism; severe accident ... See more keywords
Enhancing Workload Assessments for Validation Activities Associated with DBA and BDBA Scenarios
Sign Up to like & getrecommendations! Published in 2018 at "Nuclear Technology"
DOI: 10.1080/00295450.2017.1413922
Abstract: Abstract After the Fukushima Daiichi accident, nuclear regulators around the world have required that power reactor licensees develop more extensive emergency mitigating responses and severe accident management provisions beyond the defense-in-depth measures for design-basis accidents… read more here.
Keywords: workload; validation; enhancing workload; emergency ... See more keywords