Digital Computers in Nuclear Reactor Design

Cuthill, Elizabeth

doi:10.1016/s0065-2458(08)60356-3

Cited by 3 publications

(2 citation statements)

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“…Methods that cannot be scheduled for significant in-core data reuse include implicit time-stepping schemes, symmetric successive overrelaxation, conjugate gradient, alternating directions, and multigrid algorithms (see [55] for lower bounds for several of these). Indeed, in a 1964 survey paper on computers in nuclear reactor design [15], Cuthill remarked that alternating directions iterative methods converge faster than line-SOR methods, but are more difficult to implement efficiently out-of-core.…”

Section: Sparse Iterativementioning

confidence: 99%

A survey of out-of-core algorithms in numerical linear algebra

Toledo¹

1999

External Memory Algorithms

100

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Abstract. This paper surveys algorithms that efficiently solve linear equations or compute eigenvalues even when the matrices involved are too large to fit in the main memory of the computer and must be stored on disks. The paper focuses on scheduling techniques that result in mostly sequential data accesses and in data reuse, and on techniques for transforming algorithms that cannot be effectively scheduled. The survey covers out-of-core algorithms for solving dense systems of linear equations, for the direct and iterative solution of sparse systems, for computing eigenvalues, for fast Fourier transforms, and for N-body computations. The paper also discusses reasonable assumptions on memory size, approaches for the analysis of out-of-core algorithms, and relationships between out-of-core, cache-aware, and parallel algorithms.

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Section: Sparse Iterativementioning

confidence: 99%

A survey of out-of-core algorithms in numerical linear algebra

Toledo¹

1999

External Memory Algorithms

100

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“…The application of high-speed computers to nuclear reactor calculations dates from the beginning of the parallel development of high-speed digital computers and nuclear chain reactors [Cuthill, 1964]. Digital computers have become a basic tool in nuclear reactor design.…”

Section: Reactor Core Analysis Nuclear Fuel Management and Nuclear mentioning

confidence: 99%