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Calculation of Sub-Critical Multiplication Using a Simplified Fission Matrix Method

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This article is published in Transactions of the American Nuclear Society.The article was published on 2009-12-01 and is currently open access. It has received 10 citations till now. The article focuses on the topics: Multiplication & Fission.

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The RAPID Fission Matrix Approach to Reactor Core Criticality Calculations

TL;DR: The real-time analysis for Particle transport and in-situ detection (RAPID) code as discussed by the authors uses a unique, extremely fast, fission matrix-based methodology to compute the eigenvalue, and three-dimensional, pi...
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An iterative fission matrix scheme for calculating steady-state power and critical control rod position in a TRIGA reactor

TL;DR: In this paper, the authors demonstrate a fission matrix methodology to calculate the fission source in the Penn State Breazeale Reactor while accounting for control rod movement and fuel temperature feedback.
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A local fission matrix correction method for heterogeneous whole core transport with RAPID

TL;DR: In this paper, two methods are discussed that uses a set of small, 2D, 2 × 2 assembly fixed source fission matrix calculations in order to correct the RAPID 3-D whole-core matrix.
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Fission matrix homogenization and iterative convergence in RAPID

TL;DR: A combination of all acceleration techniques speeds up the RAPID calculation on BEAVRS benchmark problem by three times, with only a negligible loss of accuracy.
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A correction method for RAPID fission matrix calculations with control rod movement

TL;DR: The RAPID radiation transport code, based on a fission matrix combination method, was initially designed for spent fuel systems but has been applied on reactor core neutronics analysis.
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