APROS BWR plant analyser with 3-D core

Eija Karita Puska; Sixten Norrman

APROS BWR plant analyser with 3-D core

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

Abstract

The paper presents APROS BWR, Plant Analyser with 3-D core model. The model describes the Finnish Olkiluoto BWR plant owned by the TVO utility. In the APROS 3-D core model the neutronics part was described with 500 quadratic fuel assemblies. Two identical fuel assemblies were placed into each one-dimensional thermal hydraulic channel that were described either with the five- or the six-equation thermal hydraulic model. Thus, there are two independent plant analyser models with 3-D core, the five-equation plant analyser and the six-equation plant analyser. The results of the APROS 3-D core model with the alternative thermal hydraulics models are compared with the steady state results of the plant design code results. Three particular plant transients are calculated with the 3-D plant analyser using the five-equation thermal hydraulic model. The paper contains also a qualitative comparison of the transient results with the results of similar transients using 1-D core model.

Original language	English
Title of host publication	CD-ROM Proceedings of the 7th International Conference on Nuclear Engineering
Publisher	Japan Society of Mechanical Engineers
Number of pages	10
Publication status	Published - 1999
MoE publication type	Not Eligible
Event	7th International Conference on Nuclear Engineering, ICONE-7 - Tokyo, Japan Duration: 19 Apr 1999 → 23 Apr 1999

Conference

Conference	7th International Conference on Nuclear Engineering, ICONE-7
Country/Territory	Japan
City	Tokyo
Period	19/04/99 → 23/04/99

Cite this

@inproceedings{6cc9d9c2047443c7b282fa56e29f9511,

title = "APROS BWR plant analyser with 3-D core",

abstract = "The paper presents APROS BWR, Plant Analyser with 3-D core model. The model describes the Finnish Olkiluoto BWR plant owned by the TVO utility. In the APROS 3-D core model the neutronics part was described with 500 quadratic fuel assemblies. Two identical fuel assemblies were placed into each one-dimensional thermal hydraulic channel that were described either with the five- or the six-equation thermal hydraulic model. Thus, there are two independent plant analyser models with 3-D core, the five-equation plant analyser and the six-equation plant analyser. The results of the APROS 3-D core model with the alternative thermal hydraulics models are compared with the steady state results of the plant design code results. Three particular plant transients are calculated with the 3-D plant analyser using the five-equation thermal hydraulic model. The paper contains also a qualitative comparison of the transient results with the results of similar transients using 1-D core model.",

author = "Puska, {Eija Karita} and Sixten Norrman",

note = "HUO: Full review No ISBN/ISSN found for the proceedings; 7th International Conference on Nuclear Engineering, ICONE-7 ; Conference date: 19-04-1999 Through 23-04-1999",

year = "1999",

language = "English",

booktitle = "CD-ROM Proceedings of the 7th International Conference on Nuclear Engineering",

publisher = "Japan Society of Mechanical Engineers",

address = "Japan",

}

TY - GEN

T1 - APROS BWR plant analyser with 3-D core

AU - Puska, Eija Karita

AU - Norrman, Sixten

N1 - HUO: Full review No ISBN/ISSN found for the proceedings

PY - 1999

Y1 - 1999

N2 - The paper presents APROS BWR, Plant Analyser with 3-D core model. The model describes the Finnish Olkiluoto BWR plant owned by the TVO utility. In the APROS 3-D core model the neutronics part was described with 500 quadratic fuel assemblies. Two identical fuel assemblies were placed into each one-dimensional thermal hydraulic channel that were described either with the five- or the six-equation thermal hydraulic model. Thus, there are two independent plant analyser models with 3-D core, the five-equation plant analyser and the six-equation plant analyser. The results of the APROS 3-D core model with the alternative thermal hydraulics models are compared with the steady state results of the plant design code results. Three particular plant transients are calculated with the 3-D plant analyser using the five-equation thermal hydraulic model. The paper contains also a qualitative comparison of the transient results with the results of similar transients using 1-D core model.

AB - The paper presents APROS BWR, Plant Analyser with 3-D core model. The model describes the Finnish Olkiluoto BWR plant owned by the TVO utility. In the APROS 3-D core model the neutronics part was described with 500 quadratic fuel assemblies. Two identical fuel assemblies were placed into each one-dimensional thermal hydraulic channel that were described either with the five- or the six-equation thermal hydraulic model. Thus, there are two independent plant analyser models with 3-D core, the five-equation plant analyser and the six-equation plant analyser. The results of the APROS 3-D core model with the alternative thermal hydraulics models are compared with the steady state results of the plant design code results. Three particular plant transients are calculated with the 3-D plant analyser using the five-equation thermal hydraulic model. The paper contains also a qualitative comparison of the transient results with the results of similar transients using 1-D core model.

M3 - Conference article in proceedings

BT - CD-ROM Proceedings of the 7th International Conference on Nuclear Engineering

PB - Japan Society of Mechanical Engineers

T2 - 7th International Conference on Nuclear Engineering, ICONE-7

Y2 - 19 April 1999 through 23 April 1999

ER -

APROS BWR plant analyser with 3-D core

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