kth.sePublications KTH
System disruptions
There are recurring service disruptions on some of the search portals due to high traffic. We are working to resolve the issue, you may temporarily encounter an error message.
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
Optimal time step length and statistics in Monte Carlo burnup simulations
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering.ORCID iD: 0000-0002-7943-7517
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering.ORCID iD: 0000-0003-4878-6711
2020 (English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 139, article id 107244Article in journal (Refereed) Published
Abstract [en]

Monte Carlo burnup simulations continue to be seen as computationally very expensive numerical routines despite recent developments of associated methods. Here, we suggest a way of improving the computing efficiency via optimisation of the length of the time steps and the number of neutron histories that are simulated at each Monte Carlo criticality run. So far, users of Monte Carlo burnup codes have been required to set these parameters at will; however, an inadequate choice of these free parameters can severely worsen the computing efficiency. We have tested a large number of combinations of the free parameters on a simplified and fast solver, and we have observed that the computing efficiency was maximized when the computing cost of all Monte Carlo neutron transport calculations (summed over all time steps) was approximately comparable to costs of other procedures (all depletion simulations, the loading and processing of neutron cross sections, etc.). In this technical note, we demonstrate these results, and we also derive a simple theoretical model of the convergence of Monte Carlo burnup simulations that conforms to these numerical results. Here, we also suggest a straightforward way to automatise the selection of the optimal values of the free parameters for Monte Carlo burnup simulations.

Place, publisher, year, edition, pages
Elsevier, 2020. Vol. 139, article id 107244
Keywords [en]
Efficiency, Monte Carlo burnup calculations, Optimisation, Statistics, Time step length
National Category
Physical Sciences
Identifiers
URN: urn:nbn:se:kth:diva-267784DOI: 10.1016/j.anucene.2019.107244ISI: 000517662400049Scopus ID: 2-s2.0-85076440384OAI: oai:DiVA.org:kth-267784DiVA, id: diva2:1411778
Note

QC 20200304

Available from: 2020-03-04 Created: 2020-03-04 Last updated: 2022-06-26Bibliographically approved
In thesis
1. Towards Efficient Monte Carlo Calculations in Reactor Physics: Criticality, Kinetics and Burnup Problems
Open this publication in new window or tab >>Towards Efficient Monte Carlo Calculations in Reactor Physics: Criticality, Kinetics and Burnup Problems
2021 (English)Doctoral thesis, comprehensive summary (Other academic)
Abstract [en]

This thesis presents a compilation of work focused on Monte Carlo crit-icality, kinetics and burnup calculations in reactor physics. Performing suchcalculations usually comes at a high computing cost. Therefore, the main mo-tivation behind the presented work is lowering the computing cost of MonteCarlo calculations. To this end, three new methods for improving the comput-ing efficiency are proposed: a method for neutron population control in MonteCarlo criticality calculations; a hybrid stochastic-deterministic response ma-trix method for reactor kinetics calculations; and an optimisation method forMonte Carlo burnup calculations.

The first method gradually increases the neutron population size over thesuccessive cycles in Monte Carlo criticality calculations. This enables fasterfission source iterations at the beginning of a calculation where the sourcemay contain errors from the initial cycle while at the same time preventingthe source bias from dominating the error later in the calculation. The methodis tested on a set of full-core PWR criticality calculations.

The second method is based on the response matrix formalism which de-scribes a system by a set of response functions. The response functions arecomputed during Monte Carlo criticality calculations. These functions arethen used in a deterministic set of equations for solving a space-time depen-dent problem. The method is demonstrated on a set of absorber movementtransients in a PWR-type mini-core.

The third method sets the time step length and the number of neutronhistories simulated during each time step of Monte Carlo burnup calculationsaccording to the fraction of the computing cost assigned to the depletion solu-tions (and other procedures that are repeatedly executed before starting theactive cycles) and the overall computing cost of a Monte Carlo burnup calcu-lation. Optimal values of this fraction are studied in a set of test calculations.

Additionally, numerical tests on tally error convergence in Monte Carlocriticality calculations and stability of Monte Carlo burnup calculations arepresented. The context and the outcomes of the work are summarized inthe main body of the thesis while the details are presented in the appendedpublications.

Abstract [sv]

Denna avhandling presenterar en sammanställning av arbete fokuseratpå Monte Carlo-kriticitets, kinetik och utbränningsberäkningar inom reak-torfysik. Att utföra sådana beräkningar innebär vanligtvis en hög datorkost-nad. Därför är den främsta motivationen bakom det presenterade arbetet attsänka beräkningskostnaden för Monte Carlo-beräkningar. För detta ändamålföreslås tre nya metoder för att förbättra beräkningseffektiviteten: en me-tod för neutronpopulationskontroll i Monte Carlo-kriticitetsberäkningar; enstokastisk-deterministisk responsmatrismetod för reaktorkinetikberäkningar;och en optimeringsmetod för Monte Carlo-utbränningsberäkningar.

Den första metoden ökar gradvis neutronpopulationens storlek över de påvarandra följande cyklerna i Monte Carlo-kriticitetsberäkningar. Detta möj-liggör en snabbare iteration av klyvningskällan i början av en beräkning därkällan kan innehålla fel från den inledande cykeln samtidigt som källförskjut-ningen förhindras från att dominera felet senare i beräkningen. Metoden testaspå en uppsättning helhärdskriticitesberäkningar i en PWR.

Den andra metoden är baserad på responsmatrisformalismen som beskri-ver ett system med en uppsättning responsfunktioner. Responsfunktionernaberäknas vid Monte Carlo-kriticitetsberäkningar. Dessa funktioner användssedan i en deterministisk uppsättning ekvationer för att lösa ett rum- ochtidsberoende problem. Metoden demonstreras på en uppsättning styrstavs-transienter i en minihärd av PWR-typ.

Den tredje metoden anger tidsstegslängden och antalet neutronhistori-er som simuleras under varje tidssteg i Monte Carlo-utbränningsberäkningarenligt andelen av beräkningskostnaden som tilldelas utbränningslösningarna(och andra procedurer som utförs upprepade gånger innan de aktiva cyklernastartas) och den totala beräkningskostnaden för en Monte Carlo-utbrännings-beräkning. Optimala värden för denna andel studeras i en uppsättning test-beräkningar.

Dessutom presenteras numeriska tester för felkonvergens i Monte Carlo-kriticitetsberäkningar och stabiliteten för Monte Carlo-utbränningsberäkningar.Kontexten och resultaten av arbetet sammanfattas i avhandlingens huvuddelmedan detaljerna presenteras i de bifogade publikationerna.

Place, publisher, year, edition, pages
Stockholm: KTH Royal Institute of Technology, 2021. p. 151
Series
TRITA-SCI-FOU ; 2021:41
National Category
Energy Engineering
Research subject
Physics, Nuclear Engineering
Identifiers
urn:nbn:se:kth:diva-304247 (URN)978-91-8040-037-4 (ISBN)
Public defence
2021-11-26, FD5, AlbaNova University Center, Roslagstullsbacken 21, Stockholm, 10:00 (English)
Opponent
Supervisors
Available from: 2021-11-04 Created: 2021-10-28 Last updated: 2022-06-25Bibliographically approved

Open Access in DiVA

No full text in DiVA

Other links

Publisher's full textScopus

Authority records

Dufek, JanMickus, Ignas

Search in DiVA

By author/editor
Dufek, JanMickus, Ignas
By organisation
Nuclear Engineering
In the same journal
Annals of Nuclear Energy
Physical Sciences

Search outside of DiVA

GoogleGoogle Scholar

doi
urn-nbn

Altmetric score

doi
urn-nbn
Total: 409 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