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MELCOR Capability Development for Simulation of Debris Bed Coolability
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.ORCID iD: 0000-0002-7145-3520
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 [en]
Severe accident, coolability, MELCOR, COCOMO, surrogate modeling, coupling codes, uncertainty analysis.
National Category
Energy Engineering
Research subject
Physics, Nuclear Engineering
Identifiers
URN: urn:nbn:se:kth:diva-301237ISBN: 978-91-7873-972-1 (print)OAI: oai:DiVA.org:kth-301237DiVA, id: diva2:1591358
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
List of papers
1. A sensitivity study of MELCOR nodalization for simulation of in-vessel severe accident progression in a boiling water reactor
Open this publication in new window or tab >>A sensitivity study of MELCOR nodalization for simulation of in-vessel severe accident progression in a boiling water reactor
Show others...
2019 (English)In: Nuclear Engineering and Design, ISSN 0029-5493, E-ISSN 1872-759X, Vol. 343, p. 22-37Article in journal (Refereed) Published
Abstract [en]

This paper presents a sensitivity study of MELCOR nodalization for simulation of postulated severe accidents in a Nordic boiling water reactor, with the objective to address the nodal effect on in-vessel accident progression, including thermal-hydraulic response, core degradation and relocation, hydrogen generation, source term release, melt behavior and heat transfer in the lower head, etc. For this purpose, three meshing schemes (coarse, medium and fine) of the COR package of MELCOR are chosen to analyze two severe accident scenarios: station blackout (SBO) accident and large break loss-of-coolant accident (LOCA) combined with station blackout. The comparative results of the MELCOR simulations show that the meshing schemes mainly affect the core degradation and relocation to the lower head of the reactor pressure vessel: the fine mesh leads to a delayed leveling process of a heap-like debris bed in the lower head, and a later breach of the vessel. The simulations with fine mesh also provide more detailed distributions of corium mass and temperature, as well as heat flux which is an important parameter in qualification assessment of the In-Vessel Melt Retention (IVR) strategy.

Place, publisher, year, edition, pages
ELSEVIER SCIENCE SA, 2019
Keywords
Boiling water reactor, Reactor safety, Severe accident, MELCOR simulation, Mesh sensitivity analysis
National Category
Physical Sciences
Identifiers
urn:nbn:se:kth:diva-244082 (URN)10.1016/j.nucengdes.2018.12.011 (DOI)000456923500003 ()2-s2.0-85059233155 (Scopus ID)
Note

QC 20190219

Available from: 2019-02-19 Created: 2019-02-19 Last updated: 2024-03-15Bibliographically approved
2. Coupled MELCOR/COCOMO analysis on quench of ex-vessel debris beds
Open this publication in new window or tab >>Coupled MELCOR/COCOMO analysis on quench of ex-vessel debris beds
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
Keywords
Severe accident; Debris bed coolability; Coupled analysis; MELCOR; COCOMO
National Category
Energy Engineering
Identifiers
urn:nbn:se:kth:diva-300765 (URN)10.1016/j.anucene.2021.108643 (DOI)000703346100011 ()2-s2.0-85113690379 (Scopus ID)
Note

QC 20210906

Available from: 2021-09-02 Created: 2021-09-02 Last updated: 2022-12-13Bibliographically approved
3. Development and application of a surrogate model for quick estimation of ex-vessel debris bed coolability
Open this publication in new window or tab >>Development and application of a surrogate model for quick estimation of ex-vessel debris bed coolability
2020 (English)In: Nuclear Engineering and Design, ISSN 0029-5493, E-ISSN 1872-759X, Vol. 370, article id 110898Article in journal (Refereed) Published
Abstract [en]

During a hypothetical severe accident of a Nordic boiling water reactor (BWR), an ex-vessel particulate debris bed is expected to form in the flooded lower drywell due to melt-coolant interactions after vessel failure. The key parameter to evaluate debris bed coolability is the dryout heat flux (DHF) or dryout power density, representing the limit of heat removal capacity by the coolant. Several numerical codes such as COCOMO have been developed to simulate thermal hydraulics in multi-dimensional debris beds and predict the cooling limit, but they are computationally expensive and not suitable for probabilistic risk analysis. This paper aims to develop a surrogate model which can serve as a quick-estimate tool for the dryout power density of a heap-like debris bed in a saturated water pool. The dryout power density predicted from the COCOMO code is treated as the full model. A characteristic factor is introduced as the dryout power density ratio between the multi-dimensional debris bed (predicted by COCOMO code) and the corresponding one-dimensional debris bed (predicted by Lipinski 0-D model). The characteristic factor is correlated by the Kriging method with six parameters: bed porosity, particle diameter, debris mass, bed slope, cavity radius and containment pressure. After the surrogate model is trained and validated, it is employed to analyze the coolability of prototypical debris beds of a reference Nordic BWR, given the bed mass and containment pressure from MELCOR simulation. Coolability maps are produced as quick look-up diagrams for identification of coolable domain with the variation of porosity, particle diameter and slope angle. A preliminary uncertainty analysis is performed to demonstrate the effect of uncertain input parameters on non-coolable domain.

Place, publisher, year, edition, pages
Elsevier BV, 2020
National Category
Energy Engineering
Identifiers
urn:nbn:se:kth:diva-289000 (URN)10.1016/j.nucengdes.2020.110898 (DOI)000598782100008 ()2-s2.0-85094905215 (Scopus ID)
Note

QC 20210122

Available from: 2021-01-22 Created: 2021-01-22 Last updated: 2024-03-15Bibliographically approved

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