Methods of studying the effect of rough surfaces on reactivity in two-dimensional reactor physics problems
- 1. Nuclear Engineering Group, Department of Mechanical Engineering, City and Guilds Building, Imperial College London, Exhibition Road, South Kensington, London, SW7 2AZ (United Kingdom)
Description
Highlights: • Approximations of small-scale interface and boundary perturbations. • Homotopy and homogenisation approximations were applied to cylindrical pincells. • Perturbations additionally applied to the Feinberg-Galanin method. • Perturbation methods provided a reasonable estimate at a lower computational cost. - Abstract: Rough and perturbed surfaces are examined in the field of reactor physics using homotopy, homogenisation and the Feinberg-Galanin method. The homotopy method allows a problem with a perturbed interface to be represented as an unperturbed problem with a modified boundary condition. Perturbation theory was applied to this method and the results were studied for the neutron transport equation, the neutron diffusion approximation and a hybrid ABH-diffusion approximation. The homogenisation of surface roughness in the fuel-moderator interface was also examined and compared to the homotopy approach. Finally, the effect of larger-scale geometric uncertainties was studied using the Feinberg-Galanin approach. The effectiveness of the methods is determined by examining the change in effective multiplication factor keff examined both directly and via the six-factor formula. Analytic solutions to approximations of perturbation theory differentials were capable of accurately predicting the change in keff when compared to numerical solutions. Examining a change in fuel pin radius of 20 µm, we find that for water moderated systems the overall change in is close to 70 pcm and for graphite systems it is 18 pcm. This shows that water and graphite moderated cores are sensitive to small changes in geometry.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2019.03.002Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2019.03.002;
- PII
- S0306454919301276;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 130
- Journal Page Range
- p. 493-511
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51012855
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ANALYTICAL SOLUTION; BOUNDARY CONDITIONS; CYLINDRICAL CONFIGURATION; FUEL PINS; GEOMETRY; GRAPHITE; MULTIPLICATION FACTORS; NEUTRON DIFFUSION EQUATION; NEUTRON TRANSPORT THEORY; NUMERICAL SOLUTION; PERTURBATION THEORY; REACTIVITY; REACTOR PHYSICS; TWO-DIMENSIONAL CALCULATIONS; WATER MODERATED REACTORS
- Descriptors DEC
- CARBON; CONFIGURATION; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; DIMENSIONLESS NUMBERS; ELEMENTS; EQUATIONS; FUEL ELEMENTS; MATHEMATICAL SOLUTIONS; MATHEMATICS; MINERALS; NONMETALS; PARTIAL DIFFERENTIAL EQUATIONS; PHYSICS; REACTOR COMPONENTS; REACTORS; TRANSPORT THEORY
Optional Information
- Notes
- © 2019 Elsevier Ltd. All rights reserved.