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Coupled MELCOR/COCOMO analysis on quench of ex-vessel debris beds
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.ORCID iD: 0000-0002-7145-3520
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.ORCID iD: 0000-0002-8917-7720
2022 (English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 165, article id 108643Article in journal (Refereed) Published
Abstract [en]

The cornerstone of severe accident strategy of Nordic BWRs is to flood the reactor cavity for the long-termcoolability of an ex-vessel debris bed. As a prerequisite of the long-term coolability, the hot debris bedformed from fuel coolant interactions (FCI) should be quenched. In the present study, coupling of theMELCOR and COCOMO codes is realized with the aim to analyze the quench process of an ex-vessel debrisbed under prototypical condition of a Nordic BWR. In this coupled simulation, MELCOR performs an integralanalysis of accident progression, and COCOMO performs the thermal–hydraulic analysis of the debrisbed in the flooded cavity. The effective diameter of the particles is investigated. The discussion on thebed’s shape shows a significant effect on the propagation of the quench front, due to different flow patterns.Compared with MELCOR standalone simulation, the coupled simulation predicts earlier cavity poolsaturation and containment venting.

Place, publisher, year, edition, pages
Elsevier BV , 2022. Vol. 165, article id 108643
Keywords [en]
Severe accident; Debris bed coolability; Coupled analysis; MELCOR; COCOMO
National Category
Energy Engineering
Identifiers
URN: urn:nbn:se:kth:diva-300765DOI: 10.1016/j.anucene.2021.108643ISI: 000703346100011Scopus ID: 2-s2.0-85113690379OAI: oai:DiVA.org:kth-300765DiVA, id: diva2:1590342
Note

QC 20210906

Available from: 2021-09-02 Created: 2021-09-02 Last updated: 2022-12-13Bibliographically approved
In thesis
1. MELCOR Capability Development for Simulation of Debris Bed Coolability
Open this publication in new window or tab >>MELCOR Capability Development for Simulation of Debris Bed Coolability
2021 (English)Doctoral thesis, comprehensive summary (Other academic)
Abstract [en]

The severe accident management (SAM) strategy for a Nordic boiling water reactor (BWR) employs cavity flooding prior to vessel failure, so that the core melt (corium) discharged from the vessel could fragment and form a particulate debris bed. The key to the success of this SAM strategy is the coolability of ex-vessel debris beds.

The safety analysis involves knowledge about the reactor response to severe accidents under this SAM strategy, which requires the integral simulation of a system code such as MELCOR. Since currently the MELCOR code lacks the modeling of ex-vessel particulate debris beds, the present study aims to develop the capability of MELCOR for the simulation of debris bed coolability through the coupling of MELCOR with other codes, which are dedicated to this phenomenon.

The study is started from the qualification of a MELCOR model for severe accident analysis of a reference Nordic BWR, with the aim to help identify a proper core nodalization. For this purpose, three different core meshes (coarse, medium, and fine) are employed to obtain their impacts on corium release conditions. It is found the coarse mesh is sufficient in the present study, since it is not only computationally efficient, but also predicting earlier vessel failure and faster corium release, providing a more conservative condition for debris bed coolability analysis.

Two couplings are then adopted: (i) coupling of MELCOR with the COCOMO code, which is a mechanistic code for simulation of thermal hydraulics in debris beds; and (ii) coupling of MELCOR with a surrogate model developed in the present study. The first method can simulate the transient behavior of a debris bed during quench process. The second method can efficiently predict the coolability limit (dryout power) required in safety analysis. The surrogate model is developed based on the COCOMO prediction of two-dimensional debris beds.

The developed simulation tools, including the coupled codes and the surrogate model, are applied to the safety analysis of the reference Nordic BWR. The coupled MELCOR/COCOMO simulation is used to investigate the debris bed properties. The effective particle diameter is found as approximately 10% larger than the surface mean diameter of a debris bed with distributed sizes, quantified by the quench rate. For the effect of debris bed shape, it shows a faster quench process with a lower bed slope angle. The quench front propagation as well as the responses of local temperature and containment pressure are obtained.

The coupled MELCOR/surrogate model simulation is performed to estimate the coolability of ex-vessel vessel debris beds. The results show that debris beds are coolable under prototypical conditions with probable bed properties. The surrogate model is used to generate coolability maps, which show the debris bed coolability with the variation of bed properties. The sensitivity analysis indicates that the porosity and the geometry are the most influential to coolability limit. An uncertainty analysis methodology is proposed to obtain the probability of non-coolable debris beds.

Abstract [sv]

Strategin för hantering av svåra haverier (SAM) från ett vattenfyllt nedre primärutrymme för nordiska kokvattenreaktorerna (BWR), så att härdsmältan (corium) som läckt ut från reaktortanken kan fragmentera och bilda en partikelformiggrusbädd. Nyckeln till framgången med denna SAM-strategi är kylbarheten av härdsmältan efter genomsmältning av reaktortanken (ex-vessel). Säkerhetsanalysen fordrar kunskap om reaktorns respons på svåra haverier enligt denna SAM-strategi, detta kräver en integrerad simulering av händelsen med en systemkod, som MELCOR. Eftersom MELCOR för närvarande saknar modellering av grusbäddar efter genomsmältning av reaktortanken, syftar denna studie på att utveckla MELCOR:s förmåga att simulera grusbäddars kylbarhet genom koppling av MELCOR till andra koder som är avsedda för detta fenomen. Studien utgår från utvärdering av en MELCOR-modell för analys av svåra haverier i en representativmodell för en nordisk kokarvattenreaktor. Syftet är att identifiera en korrekt härd nodalisering. Tre olika nodtyper (grovmaskig, medelmaskig och finmaskig) för nodalisering av härden används för att studera deras effekt på simuleringen av härdsmältans utsläpp. Den grovmaskiga nodaliseringen bedömdes lämpligast för den nuvarande studien, eftersom det inte bara är beräkningseffektivt, utan även förutspår tidigare reaktortankbrått och snabbare utsläpp av härdsmältan, vilket ger ett mer konservativt tillstånd för analys av kylbarhet av grusbädden. Två kopplingar antas sedan: i) koppling av MELCOR med den mekaniska koden COCOMO avsedd för simulering av termohydraulik i grusbäddar; och ii) koppling av MELCOR med en surrogatmodell utvecklad under denna studie. Den första metoden kan simulera störningar hos en grusbädd under kylningsprocessen. Den andra metoden kan effektivt förutsäga marginalerna mot torrkokning (dryout power) som krävs i säkerhetsanalysen. Surrogatmodellen är utvecklad baserat på COCOMOsförutsägelsen av tvådimensionella grusbäddar. IV De utvecklade simuleringsverktygen, inklusive de koppladekoderna och surrogatmodellen, tillämpas på säkerhetsanalysen av en referens nordisk kokarvattenreaktor BWR. Den kopplade MELCOR/COCOMO simuleringen används för att undersöka grusbäddens egenskaper. Den effektiva partikeldiametern är cirka 10% större än medeldiameter i för grusbäddsytaspartiklar med distribuerade partikelstorlekar som kvantifierats av snabbt nedkylningshastigheten. Grusbäddens form påverkar effekten av nedkylningsprocessen, en lägre lutningsvinkel ökar nedkylningen. Nedkylningsfrontens utbredning så som den lokala temperatur och inneslutningstrycket erhålls. Den kopplade MELCOR/surrogatmodellsimuleringen utförs för att uppskatta kylbarheten hos grusbäddar efter genomsmältning av reaktortanken. Resultaten visar att grusbäddar kan kylas under prototypiska förhållanden med sannolika grusbäddegenskaper. Surrogatmodellen används för att generera kylbarhetskartor, som beskriver systematiskt grusbäddens kylbarhet beroende på variation i grusbäddegenskaper. Känslighetsanalyser indikerar att porositet och geometrin är mest inflytelserika för marginalerna mot torrkokning. En metod för osäkerhetsanaly

Place, publisher, year, edition, pages
Stockholm, Sweden: KTH Royal Institute of Technology, 2021. p. 59
Series
TRITA-SCI-FOU 2021:31
Keywords
Severe accident, coolability, MELCOR, COCOMO, surrogate modeling, coupling codes, uncertainty analysis.
National Category
Energy Engineering
Research subject
Physics, Nuclear Engineering
Identifiers
urn:nbn:se:kth:diva-301237 (URN)978-91-7873-972-1 (ISBN)
Public defence
2021-09-23, Via Zoom https://kth-se.zoom.us/j/61455360179, 09:30 (English)
Opponent
Supervisors
Available from: 2021-09-06 Created: 2021-09-06 Last updated: 2022-12-13Bibliographically approved

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Chen, YangliZhang, HuiminMa, Weimin

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