THE PLTEMP V2.1 CODE

RERTR
Reduced Enrichment for Research and Test Reactors
Nuclear Science and Engineering Division at Argonne

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Abstracts and Available Papers Presented at the
2003 International RERTR Meeting

THE PLTEMP V2.1 CODE

A.P. Olson

RERTR Program
Nuclear Engineering Division
Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439 - USA

ABSTRACT

Recent improvements to the computer code PLTEMP/ANL V2.1 are described. A new iterative, error-minimization solution technique is used to obtain the thermal distribution both within each fuel plate, and along the axial length of each coolant channel. A new, radial geometry solution is available for tube-type fuel assemblies. Software comparisons of these and other new models are described. Applications to Russian-designed IRT-type research reactors are described.

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Contact:
Dr. Arne P. Olson
Nuclear Engineer
Nuclear Engineering Division
Argonne National Laboratory
9700 South Cass Avenue
Argonne, IL 60439

Phone: (630) 252-9756
Fax: (630) 252-5161

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Last modified on July 29, 2008 11:34 +0200

Abstracts and Available Papers Presented at the2003 International RERTR Meeting

THE PLTEMP V2.1 CODE

Abstracts and Available Papers Presented at the
2003 International RERTR Meeting