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Application of response matrix method to transient simulations of nuclear systems
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering.ORCID iD: 0000-0003-4878-6711
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering.ORCID iD: 0000-0002-7943-7517
2020 (English)In: International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020, EDP Sciences , 2020, p. 786-793Conference paper, Published paper (Refereed)
Abstract [en]

Until recently, reactor transient problems were exclusively solved by approximate deterministic methods. The increase in available computing power made it feasible to approach the transient analyses with time-dependent Monte Carlo methods. These methods offer the first-principle solution to the space-time evolution of reactor power by explicitly tracking prompt neutrons, precursors of delayed neutrons and delayed neutrons in time and space. Nevertheless, a very significant computing cost is associated with such methods. The general benefits of the Monte Carlo approach may be retained at a reduced computing cost by applying a hybrid stochastic-deterministic computing scheme. Among such schemes are those based on the fission matrix and the response matrix formalisms. These schemes aim at estimating a variant of the Greens function during a Monte Carlo transport calculation, which is later used to formulate a deterministic approach to solving a space-time dependent problem. In this contribution, we provide an overview of the time-dependent response matrix method, which describes a system by a set of response functions. We have recently suggested an approach where the functions are determined during a Monte Carlo criticality calculation and are then used to deterministically solve the space-time behaviour of the system. Here, we compare the time-dependent response matrix solution with the transient fission matrix and the time-dependent Monte Carlo solutions for a control rod movement problem in a mini-core reactor geometry. The response matrix formalism results in a set of loosely connected equations which offers favourable scaling properties compared to the methods based on the fission matrix formalism.

Place, publisher, year, edition, pages
EDP Sciences , 2020. p. 786-793
Keywords [en]
Monte Carlo, Response Matrix Method, Transient Analyses, Matrix algebra, Neutrons, Stochastic systems, Transient analysis, Criticality calculations, Deterministic approach, Deterministic methods, Monte Carlo approach, Response matrix methods, Space-time evolution, Time-dependent response, Transport calculation, Monte Carlo methods
National Category
Subatomic Physics
Identifiers
URN: urn:nbn:se:kth:diva-301004DOI: 10.1051/epjconf/202124704014Scopus ID: 2-s2.0-85108440677OAI: oai:DiVA.org:kth-301004DiVA, id: diva2:1591166
Conference
2020 International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020, 28 March 2020 through 2 April 2020, Cambridge, 28 March 2020 - 2 April 2020
Note

QC 20210906

Available from: 2021-09-06 Created: 2021-09-06 Last updated: 2022-06-25Bibliographically 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

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Mickus, IgnasDufek, Jan

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