Three-dimensional variational nodal transport methods for cartesian, triangular, and hexagonal criticality calculations

C. B. Carrico; Elmer E Lewis; G. Palmiotti

doi:10.13182/NSE92-1

Three-dimensional variational nodal transport methods for cartesian, triangular, and hexagonal criticality calculations

C. B. Carrico^*, Elmer E Lewis, G. Palmiotti

^*Corresponding author for this work

Mechanical Engineering

Research output: Contribution to journal › Article › peer-review

77 Scopus citations

Abstract

The variational nodal transport method is generalized for the effective treatment of multi-group criticality problems in two and three dimensions. A symbolic manipulation procedure is developed to achieve the fully automated generation of nodal response matrices in three-dimensional and non-Cartesian geometries. A red-black partitioned matrix algorithm for accelerating the solutions of the resulting within-group equations is presented, and its efficacy demonstrated. The methods are implemented as an option of the Argonne National Laboratory code DIF3D and applied to a series of five benchmark problems in x-y-z and hexagonal-z geometries. For reactors with large transport effects, the variational P₃ calculations agree with accurate Monte Carlo eigenvalues to within a few hundredths to a few tenths of a percent while requiring Cray X-MP computing times ranging from tens to hundreds of seconds.

Original language	English (US)
Pages (from-to)	168-179
Number of pages	12
Journal	Nuclear Science and Engineering
Volume	111
Issue number	2
DOIs	https://doi.org/10.13182/NSE92-1
State	Published - Jan 1 1992

ASJC Scopus subject areas

Nuclear Energy and Engineering

Access to Document

10.13182/NSE92-1

Fingerprint Dive into the research topics of 'Three-dimensional variational nodal transport methods for cartesian, triangular, and hexagonal criticality calculations'. Together they form a unique fingerprint.

Cite this

@article{4de7ba7077ed4a85a1ba4586c26ea308,

title = "Three-dimensional variational nodal transport methods for cartesian, triangular, and hexagonal criticality calculations",

abstract = "The variational nodal transport method is generalized for the effective treatment of multi-group criticality problems in two and three dimensions. A symbolic manipulation procedure is developed to achieve the fully automated generation of nodal response matrices in three-dimensional and non-Cartesian geometries. A red-black partitioned matrix algorithm for accelerating the solutions of the resulting within-group equations is presented, and its efficacy demonstrated. The methods are implemented as an option of the Argonne National Laboratory code DIF3D and applied to a series of five benchmark problems in x-y-z and hexagonal-z geometries. For reactors with large transport effects, the variational P3 calculations agree with accurate Monte Carlo eigenvalues to within a few hundredths to a few tenths of a percent while requiring Cray X-MP computing times ranging from tens to hundreds of seconds.",

author = "Carrico, {C. B.} and Lewis, {Elmer E} and G. Palmiotti",

year = "1992",

month = jan,

day = "1",

doi = "10.13182/NSE92-1",

language = "English (US)",

volume = "111",

pages = "168--179",

journal = "Nuclear Science and Engineering",

issn = "0029-5639",

publisher = "American Nuclear Society",

number = "2",

}

TY - JOUR

T1 - Three-dimensional variational nodal transport methods for cartesian, triangular, and hexagonal criticality calculations

AU - Carrico, C. B.

AU - Lewis, Elmer E

AU - Palmiotti, G.

PY - 1992/1/1

Y1 - 1992/1/1

N2 - The variational nodal transport method is generalized for the effective treatment of multi-group criticality problems in two and three dimensions. A symbolic manipulation procedure is developed to achieve the fully automated generation of nodal response matrices in three-dimensional and non-Cartesian geometries. A red-black partitioned matrix algorithm for accelerating the solutions of the resulting within-group equations is presented, and its efficacy demonstrated. The methods are implemented as an option of the Argonne National Laboratory code DIF3D and applied to a series of five benchmark problems in x-y-z and hexagonal-z geometries. For reactors with large transport effects, the variational P3 calculations agree with accurate Monte Carlo eigenvalues to within a few hundredths to a few tenths of a percent while requiring Cray X-MP computing times ranging from tens to hundreds of seconds.

AB - The variational nodal transport method is generalized for the effective treatment of multi-group criticality problems in two and three dimensions. A symbolic manipulation procedure is developed to achieve the fully automated generation of nodal response matrices in three-dimensional and non-Cartesian geometries. A red-black partitioned matrix algorithm for accelerating the solutions of the resulting within-group equations is presented, and its efficacy demonstrated. The methods are implemented as an option of the Argonne National Laboratory code DIF3D and applied to a series of five benchmark problems in x-y-z and hexagonal-z geometries. For reactors with large transport effects, the variational P3 calculations agree with accurate Monte Carlo eigenvalues to within a few hundredths to a few tenths of a percent while requiring Cray X-MP computing times ranging from tens to hundreds of seconds.

UR - http://www.scopus.com/inward/record.url?scp=0026872239&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=0026872239&partnerID=8YFLogxK

U2 - 10.13182/NSE92-1

DO - 10.13182/NSE92-1

M3 - Article

AN - SCOPUS:0026872239

VL - 111

SP - 168

EP - 179

JO - Nuclear Science and Engineering

JF - Nuclear Science and Engineering

SN - 0029-5639

IS - 2

ER -