CiteExport$(function(){PrimeFaces.cw("TieredMenu","widget_formSmash_upper_j_idt144",{id:"formSmash:upper:j_idt144",widgetVar:"widget_formSmash_upper_j_idt144",autoDisplay:true,overlay:true,my:"left top",at:"left bottom",trigger:"formSmash:upper:exportLink",triggerEvent:"click"});}); $(function(){PrimeFaces.cw("OverlayPanel","widget_formSmash_upper_j_idt145_j_idt147",{id:"formSmash:upper:j_idt145:j_idt147",widgetVar:"widget_formSmash_upper_j_idt145_j_idt147",target:"formSmash:upper:j_idt145:permLink",showEffect:"blind",hideEffect:"fade",my:"right top",at:"right bottom",showCloseIcon:true});});

Development of New Monte Carlo Methods in Reactor Physics: Criticality, Non-Linear Steady-State and Burnup ProblemsPrimeFaces.cw("AccordionPanel","widget_formSmash_some",{id:"formSmash:some",widgetVar:"widget_formSmash_some",multiple:true}); PrimeFaces.cw("AccordionPanel","widget_formSmash_all",{id:"formSmash:all",widgetVar:"widget_formSmash_all",multiple:true});
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PrimeFaces.cw("AccordionPanel","widget_formSmash_responsibleOrgs",{id:"formSmash:responsibleOrgs",widgetVar:"widget_formSmash_responsibleOrgs",multiple:true}); 2009 (English)Doctoral thesis, comprehensive summary (Other academic)
##### Abstract [en]

##### Place, publisher, year, edition, pages

Stockholm: Universitetsservice US AB , 2009. , p. xi, 49
##### Series

Trita-FYS, ISSN 0280-316X ; 2009:20
##### Keyword [en]

Monte Carlo, reactor physics, fission source, inactive cycles, convergence, burnup, steady-state, criticality, eigenvalue
##### National Category

Subatomic Physics
##### Identifiers

URN: urn:nbn:se:kth:diva-10602ISBN: 978-91-7415-366-8 (print)OAI: oai:DiVA.org:kth-10602DiVA, id: diva2:220577
##### Public defence

2009-06-11, Sal FA32, AlbaNova, Roslagstullsbacken 21, Stockholm, 13:15 (English)
##### Opponent

PrimeFaces.cw("AccordionPanel","widget_formSmash_j_idt467",{id:"formSmash:j_idt467",widgetVar:"widget_formSmash_j_idt467",multiple:true});
##### Supervisors

PrimeFaces.cw("AccordionPanel","widget_formSmash_j_idt473",{id:"formSmash:j_idt473",widgetVar:"widget_formSmash_j_idt473",multiple:true});
#####

PrimeFaces.cw("AccordionPanel","widget_formSmash_j_idt479",{id:"formSmash:j_idt479",widgetVar:"widget_formSmash_j_idt479",multiple:true});
##### Note

QC 20100709Available from: 2009-06-04 Created: 2009-06-01 Last updated: 2010-07-16Bibliographically approved
##### List of papers

The Monte Carlo method is, practically, the only approach capable of giving detail insight into complex neutron transport problems. In reactor physics, the method has been used mainly for determining the *k*_{eff} in criticality calculations. In the last decade, the continuously growing computer performance has allowed to apply the Monte Carlo method also on simple burnup simulations of nuclear systems. Nevertheless, due to its extensive computational demands the Monte Carlo method is still not used as commonly as deterministic methods.

One of the reasons for the large computational demands of Monte Carlo criticality calculations is the necessity to carry out a number of inactive cycles to converge the fission source. This thesis presents a new concept of fission matrix based Monte Carlo criticality calculations where inactive cycles are not required. It is shown that the fission matrix is not sensitive to the errors in the fission source, and can be thus calculated by a Monte Carlo calculation without inactive cycles. All required results, including *k*_{eff}, are then derived via the final fission matrix. The confidence interval for the estimated *k*_{eff} can be conservatively derived from the variance in the fission matrix. This was confirmed by numerical test calculations of Whitesides's ``*k*_{eff} of the world problem'' model where other Monte Carlo methods fail to estimate the confidence interval correctly unless a large number of inactive cycles is simulated.

Another problem is that the existing Monte Carlo criticality codes are not well shaped for parallel computations; they cannot fully utilise the processing power of modern multi-processor computers and computer clusters. This thesis presents a new parallel computing scheme for Monte Carlo criticality calculations based on the fission matrix. The fission matrix is combined over a number of independent parallel simulations, and the final results are derived by means of the fission matrix. This scheme allows for a practically ideal parallel scaling since no communication among the parallel simulations is required, and no inactive cycles need to be simulated.

When the Monte Carlo criticality calculations are sufficiently fast, they will be more commonly applied on complex reactor physics problems, like non-linear steady-state calculations and fuel cycle calculations. This thesis develops an efficient method that introduces thermal-hydraulic and other feedbacks into the numerical model of a power reactor, allowing to carry out a non-linear Monte Carlo analysis of the reactor with steady-state core conditions. The thesis also shows that the major existing Monte Carlo burnup codes use unstable algorithms for coupling the neutronic and burnup calculations; therefore, they cannot be used for fuel cycle calculations. Nevertheless, stable coupling algorithms are known and can be implemented into the future Monte Carlo burnup codes.

1. Stability and convergence problems of the Monte Carlo fission matrix acceleration methods$(function(){PrimeFaces.cw("OverlayPanel","overlay329372",{id:"formSmash:j_idt519:0:j_idt523",widgetVar:"overlay329372",target:"formSmash:j_idt519:0:partsLink",showEvent:"mousedown",hideEvent:"mousedown",showEffect:"blind",hideEffect:"fade",appendToBody:true});});

2. Fission matrix based Monte Carlo criticality calculations$(function(){PrimeFaces.cw("OverlayPanel","overlay329374",{id:"formSmash:j_idt519:1:j_idt523",widgetVar:"overlay329374",target:"formSmash:j_idt519:1:partsLink",showEvent:"mousedown",hideEvent:"mousedown",showEffect:"blind",hideEffect:"fade",appendToBody:true});});

3. An efficient parallel computing scheme for Monte Carlo criticality calculations$(function(){PrimeFaces.cw("OverlayPanel","overlay329375",{id:"formSmash:j_idt519:2:j_idt523",widgetVar:"overlay329375",target:"formSmash:j_idt519:2:partsLink",showEvent:"mousedown",hideEvent:"mousedown",showEffect:"blind",hideEffect:"fade",appendToBody:true});});

4. Stochastic Approximation for Monte Carlo Calculation of Steady-State Conditions in Thermal Reactors$(function(){PrimeFaces.cw("OverlayPanel","overlay12365",{id:"formSmash:j_idt519:3:j_idt523",widgetVar:"overlay12365",target:"formSmash:j_idt519:3:partsLink",showEvent:"mousedown",hideEvent:"mousedown",showEffect:"blind",hideEffect:"fade",appendToBody:true});});

5. Numerical Stability of Existing Monte Carlo Burnup Codes in Cycle Calculations of Critical Reactors$(function(){PrimeFaces.cw("OverlayPanel","overlay329376",{id:"formSmash:j_idt519:4:j_idt523",widgetVar:"overlay329376",target:"formSmash:j_idt519:4:partsLink",showEvent:"mousedown",hideEvent:"mousedown",showEffect:"blind",hideEffect:"fade",appendToBody:true});});

isbn
urn-nbn$(function(){PrimeFaces.cw("Tooltip","widget_formSmash_j_idt1256",{id:"formSmash:j_idt1256",widgetVar:"widget_formSmash_j_idt1256",showEffect:"fade",hideEffect:"fade",showDelay:500,hideDelay:300,target:"formSmash:altmetricDiv"});});

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