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Performance and safety evaluation of a <10 wt% 235U enriched small lead-cooled fast reactor
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Science and Engineering.ORCID iD: 0000-0001-7334-9471
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Science and Engineering.ORCID iD: 0009-0000-4237-0622
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Science and Engineering.ORCID iD: 0000-0002-6082-8913
2024 (English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 212, article id 110861Article in journal (Refereed) Published
Abstract [en]

We present the conceptual core design of a small lead-cooled fast reactor, for which a critical configuration has been achieved with a uranium enrichment of 9.9 wt%. This is a novelty for fast-neutron reactors without incorporating mixed uranium/plutonium fuel. It is shown how a reduction in uranium enrichment by two percentage points from a previously designed small lead-cooled reactor leads to an increase in conversion ratio of 20% and a significantly larger reactivity swing. The lowered enrichment gives a stronger Doppler feedback, which leads to lower temperatures during an overpower transient, despite remaining feedback coefficients being less negative. The new reactor geometry is presented along with a detailed neutronic characterisation, where whole-core reactivity feedback coefficients are derived, and depletion calculations are performed. Thereafter, we use the safety analysis code SAS4A/SASSYS-1 to demonstrate that the proposed design remains safe during enveloping unprotected transients, corresponding to Beyond Design Basis Accidents. We show how the reactor has a >2000 degrees C margin to fuel melting during an Unprotected Overpower transient and that thermally induced creep rupture of the fuel cladding tubes is a non-issue despite conservatively assuming 100% fission gas release.

Place, publisher, year, edition, pages
Elsevier BV , 2024. Vol. 212, article id 110861
Keywords [en]
SUNRISE-LFR, LEU plus, Safety analysis, Small lead-cooled reactor, ATWS, BDBA
National Category
Subatomic Physics
Identifiers
URN: urn:nbn:se:kth:diva-358823DOI: 10.1016/j.anucene.2024.110861ISI: 001385260500001Scopus ID: 2-s2.0-85203836556OAI: oai:DiVA.org:kth-358823DiVA, id: diva2:1930131
Note

QC 20250122

Available from: 2025-01-22 Created: 2025-01-22 Last updated: 2025-05-14Bibliographically 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

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Dehlin, FredrikPallarès Abril, EloiWallenius, Janne

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