Journal Article10.1016/J.ANUCENE.2015.10.014
A comparison of Monte Carlo methods for neutron leakage at assembly level
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TL;DR: In this paper, the B 1 fundamental mode approximation and the albedo search method are compared in terms of eigenvalue, multi-group homogeneous scalar fluxes and maximum pin power differences for several cell types.
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About: This article is published in Annals of Nuclear Energy. The article was published on 01 Jan 2016. The article focuses on the topics: Monte Carlo method & Leakage (electronics).
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Citations
Overview of methodology for spatial homogenization in the Serpent 2 Monte Carlo code
TL;DR: The purpose of this paper is to bring the methodological description provided in earlier publications up to date, and provide insight into the developed methods and capabilities, including their limitations and known flaws.
101
Development of a New Monte Carlo Reactor Physics code: Dissertation
Jaakko Leppänen
- 01 Jan 2007
TL;DR: In this paper, Monte Carlo based lattice transport codes are used in coupled LWR full-core analyses and typically based on few-group nodal diffusion methods to model geometry and interaction physics without major approximations.
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Analysis of a small-scale reactor core with PARCS/Serpent
Filip Fejt,Jan Frybort +1 more
TL;DR: In this article, the authors present a suitable homogenization strategy for a small core of VR-1 reactor (28.6 × 28.6 cm) realized by Serpent 2.28.1.
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•Dissertation
Analyse des erreurs induites par une modélisation simplifiée sur l’évolution des combustibles REP Impact des fuites neutroniques dans les calculs cellules
Alice Somaini
- 27 Sep 2017
TL;DR: In this paper, the authors present a model for simulating the evolution of a nuclear reaction in a parc electronucleaire, based on simulations of reacteurs nucleaires.
6
Monte Carlo method for solving a B1 equation with complex-valued buckling in asymmetric geometries and generation of directional diffusion coefficients
TL;DR: In this article, a new method for critical buckling search calculation to solve a heterogeneous B 1 equation for an asymmetric unit cell in which the critical bucking has a complex value was proposed.
3
References
•Book
Methods of Steady-State Reactor Physics in Nuclear Design
Rudi J. J. Stamm'ler,Máximo Julio Abbate +1 more
- 01 Jul 1983
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Development of a New Monte Carlo reactor physics code
Jaakko Leppänen
- 18 Jun 2007
TL;DR: An interesting near-future application for the Monte Carlo method is the generation of input parameters for deterministic reactor simulator codes, used in coupled LWR full-core analyses and typically based on fewgroup nodal diffusion methods.
Mccard : monte carlo code for advanced reactor design and analysis
TL;DR: McCARD as discussed by the authors is a Monte Carlo (MC) neutron-photon transport simulation code developed exclusively for the neutronics design of nuclear reactors and fuel systems and is capable of performing the whole-core neutronics calculations, the reactor fuel burnup analysis, the few group diffusion theory constant generation, sensitivity and uncertainty (S/U) analysis, and uncertainty propagation analysis.
150
On the use of the Serpent Monte Carlo code for few-group cross section generation
Emil Fridman,Jaakko Leppänen +1 more
TL;DR: Serpent is a recently developed 3D continuous-energy Monte Carlo (MC) reactor physics burnup calculation code as mentioned in this paper, which is specifically designed for lattice physics applications including generation of homogenized few-group constants for full-core core simulators.
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