kth.sePublications KTH
Change search
CiteExportLink to record
Permanent link

Direct link
Cite
Citation style
  • apa
  • ieee
  • modern-language-association-8th-edition
  • vancouver
  • Other style
More styles
Language
  • de-DE
  • en-GB
  • en-US
  • fi-FI
  • nn-NO
  • nn-NB
  • sv-SE
  • Other locale
More languages
Output format
  • html
  • text
  • asciidoc
  • rtf
A semi-analytical method for modelling station blackout transients in liquid metal-cooled reactors
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Science and Engineering.ORCID iD: 0000-0002-6082-8913
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Science and Engineering.ORCID iD: 0000-0001-7334-9471
2025 (English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 219, article id 111414Article in journal (Refereed) Published
Abstract [en]

A semi-analytical method for modelling station blackout performance in liquid metal reactors is developed, permitting to identify key factors determining peak temperatures during the transient, and hence to design associated passive safety systems. It is shown that integrity of the fuel cladding during this transient can be ensured by adequate dimensioning of coolant channels, the primary system and the vessel air cooling circuit. These dimensions are determined using algebraic equations and postulated values for a minimum/maximum permissible Reynolds number, dimensionless parameters for the fuel cladding tube geometry and heat sink elevation, a guard vessel height, the nominal core power, permitted temperature gradients in the vessel air cooling system and the air cooling system chimney height. The model suggests that the required coolant volume is a rapidly growing function of core power, and that this volume needs to be 40% larger in a sodium-cooled reactor than in a lead-cooled reactor.

Place, publisher, year, edition, pages
Elsevier BV , 2025. Vol. 219, article id 111414
Keywords [en]
Station blackout, Passive heat removal, Primary vessel volume
National Category
Subatomic Physics Energy Engineering
Research subject
Physics, Nuclear Engineering
Identifiers
URN: urn:nbn:se:kth:diva-363056DOI: 10.1016/j.anucene.2025.111414ISI: 001471163500001Scopus ID: 2-s2.0-105002305069OAI: oai:DiVA.org:kth-363056DiVA, id: diva2:1956082
Funder
Swedish Foundation for Strategic Research, ARC19-0043
Note

QC 20250505

Available from: 2025-05-05 Created: 2025-05-05 Last updated: 2025-06-03Bibliographically approved
In thesis
1. Design and safety analysis of a lead-cooled research reactor
Open this publication in new window or tab >>Design and safety analysis of a lead-cooled research reactor
2025 (English)Doctoral thesis, comprehensive summary (Other academic)
Abstract [en]

This compilation thesis presents work focused on the design and safety analysis of the small lead-cooled research and demonstration reactor SUNRISE-LFR–the first step toward the construction of a next-generation reactor in Sweden. Two versions of SUNRISE-LFR are introduced—the second necessitated by the lack of access to uranium enriched above 10 wt.% 235U/U. Neutronic characterization is performed using the Monte Carlo code Serpent 2, while the reactors’ behaviours during design extension conditions (DECs) are analysed using the in-house developed code BELLA and an established fast reactor safety code, SAS4A/SASSYS-1. An analytical method for designing a passively safe lead-cooled reactor is derived and used to propose the core configuration of SUNRISE-LFR. This method is subsequently expanded into a semi-analytical framework for designing the Reactor Vessel Auxiliary Cooling System (RVACS), aimed at ensuring fuel cladding survivability during unprotected station blackout (USBO) transients. The model is further extended to evaluate the impact on system temperatures during USBO transients when using nuclear fuel with different actinide compositions. It is shown that actinide compositions with low concentrations of americium and the plutonium isotope 241Pu are beneficial for cladding integrity. Finally, the thesis assesses the impact of coolant circulation on the total neutron activation of the lead coolant over the reactor’s operational lifetime. It is demonstrated that a sufficiently pure lead vector—particularly one with low silver content—could allow the coolant to be exempted from radiological control within a reasonable time frame, thereby avoiding the need for disposal in a final repository. This thesis serves as both a foundation and a stepping stone for the continued development, licensing, and eventual construction of a lead-cooled reactor in Sweden.

Abstract [sv]

Denna sammanfattningsavhandling presenterar ett arbete som fokuserar på design och säkerhetsanalys av den lilla blykylda forsknings- och demonstrationsreaktorn SUNRISE-LFR—det första steget mot att bygga nästa generations reaktor i Sverige. Två versioner av SUNRISE-LFR presenteras, där avsaknaden av tillgång till uran med en anrikning över 10 wt.% 235U/U var anledningen till att en ny design behövde tas fram. Karakterisering av reaktorernas neutronfysikaliska egenskaper har genomförts med Monte Carlokoden Serpent 2, och deras beteende under utökade konstruktionstillstånd (Design Extension Conditions, DEC) analyseras med den internt utvecklade koden BELLA samt den etablerade snabbreaktorkoden SAS4A/SASSYS-1. En analytisk metod för att designa en passivt säker blykyld reaktor härleds och används för att föreslå härdkonfigurationen för SUNRISE-LFR. Denna metod expanderas för att möjliggöra en semianalytisk dimensionering av det passiva hjälpkylsystem för reaktorkärlet (Reactor Vessel Auxiliary Cooling System, RVACS) i syfte att säkerställa bränslekapslingens integritet under en oskyddad totalförlust av elförsörjning (Unprotected Station Blackout, USBO) transient. Modellen vidareutvecklas för att utvärdera hur systemtemperaturerna påverkas under USBO transienter vid användning av kärnbränsle med olika aktinidsammansättningar. Det visas att aktinidsammansättningar med låga halter av americium och plutoniumisotopen 241Pu är gynnsamma för kapslingsintegriteten. Avhandlingen undersöker även hur kylmedelscirkulation påverkar den totala neutronaktiveringen av bly under reaktorns driftstid. Det visas att en tillräckligt ren blyvektor—särskilt med låg silverhalt—kan möjliggöra friklassning av kylmediet inom rimlig tid efter avveckling, utan behov av slutförvaring. Denna avhandling utgör både en grund och ett första steg i det fortsatta arbetet med att utveckla, licensiera och i slutändan bygga en blykyld reaktor i Sverige.

Place, publisher, year, edition, pages
Stockholm: KTH Royal Institute of Technology, 2025. p. 108
Series
TRITA-SCI-FOU ; 2025:23
Keywords
SUNRISE-LFR, Lead-cooled fast reactor, Core design, Neutronics, Safety analysis, Coolant activation, SUNRISE-LFR, Blykyld snabbreaktor, Härddesign, Neutronik, Säkerhetsanalys, Kylmedieaktivering
National Category
Subatomic Physics Energy Engineering
Research subject
Physics, Nuclear Engineering
Identifiers
urn:nbn:se:kth:diva-363357 (URN)978-91-8106-261-8 (ISBN)
Public defence
2025-06-13, F3, Lindstedtsvägen 26 & 28, https://kth-se.zoom.us/j/68258737448, Stockholm, 14:00 (English)
Opponent
Supervisors
Funder
Swedish Foundation for Strategic Research, ARC19-0043
Note

QC 2025-05-14

Available from: 2025-05-19 Created: 2025-05-14 Last updated: 2025-07-01Bibliographically approved

Open Access in DiVA

No full text in DiVA

Other links

Publisher's full textScopus

Authority records

Wallenius, JanneDehlin, Fredrik

Search in DiVA

By author/editor
Wallenius, JanneDehlin, Fredrik
By organisation
Nuclear Science and Engineering
In the same journal
Annals of Nuclear Energy
Subatomic PhysicsEnergy Engineering

Search outside of DiVA

GoogleGoogle Scholar

doi
urn-nbn

Altmetric score

doi
urn-nbn
Total: 139 hits
CiteExportLink to record
Permanent link

Direct link
Cite
Citation style
  • apa
  • ieee
  • modern-language-association-8th-edition
  • vancouver
  • Other style
More styles
Language
  • de-DE
  • en-GB
  • en-US
  • fi-FI
  • nn-NO
  • nn-NB
  • sv-SE
  • Other locale
More languages
Output format
  • html
  • text
  • asciidoc
  • rtf