Applying Nonlinear Diffusion Acceleration to the Neutron Transport k-Eigenvalue Problem with Anisotropic Scattering

نویسندگان
چکیده

برای دانلود باید عضویت طلایی داشته باشید

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

منابع مشابه

A comparison of acceleration methods for solving the neutron transport k-eigenvalue problem

Article history: Received 28 January 2014 Received in revised form 18 June 2014 Accepted 20 June 2014 Available online 28 June 2014

متن کامل

A Hybrid Approach to the Neutron Transport k-Eigenvalue Problem using NDA-based Algorithms

In order to provide more physically accurate solutions to the neutron transport equation it has become increasingly popular to use Monte Carlo simulation to model nuclear reactor dynamics. These Monte Carlo methods can be extremely expensive, so we turn to a class of methods known as hybrid methods, which combine known deterministic and stochastic techniques to solve the transport equation. In ...

متن کامل

Nonlinear acceleration methods for even-parity neutron transport

OF THESIS Submitted in Partial Fulfillment of the Requirements for the Degree of Master of Science

متن کامل

A Nonlinear Krylov Accelerator for the Boltzmann k-Eigenvalue Problem

Matthew T. Calef, Erin D. Fichtl, James S. Warsa, Markus Berndt, Neil N. Carlson, CCS-2 We compare variants of Anderson Mixing with the Jacobian-Free Newton-Krylov and Broyden methods applied to the k-eigenvalue formulation of the linear Boltzmann transport equation. We present evidence that one variant of Anderson Mixing finds solutions in the fewest number of iterations. We examine and streng...

متن کامل

RESOLUTION OF THE NEUTRON DIFFUSION EQUATION WITH SLEPc, THE SCALABLE LIBRARY FOR EIGENVALUE PROBLEM COMPUTATIONS

The objective of this work is to obtain the dominant -modes of a nuclear reactor. The underlying algebraic problem is a real generalised eigenvalue problem, which can be reduced to a standard one. A parallel code has been developed in order to be able to analyse reactors with a great level of detail. The implementation has been done using SLEPc, which is a public domain library developed by the...

متن کامل

ذخیره در منابع من


  با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید

ژورنال

عنوان ژورنال: Nuclear Science and Engineering

سال: 2015

ISSN: 0029-5639,1943-748X

DOI: 10.13182/nse14-131