Validation of PLTEMP/ANL V3.6 Code for Evaluation of Safety Margins at the BR2 Reactor

Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

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Validation of PLTEMP/ANL V3.6 Code for Evaluation of Safety Margins at the BR2 Reactor. / Kalcheva, Silva; Olson, Arne; Koonen, Edgar; Matos, James; Beeckmans de West-Meerbeeck, André (Peer reviewer).

13th International Topical Meeting on Research Reactor Fuel Management (RRFM). Brussels, Belgium, 2009.

Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

Harvard

Kalcheva, S, Olson, A, Koonen, E, Matos, J & Beeckmans de West-Meerbeeck, A 2009, Validation of PLTEMP/ANL V3.6 Code for Evaluation of Safety Margins at the BR2 Reactor. in 13th International Topical Meeting on Research Reactor Fuel Management (RRFM). Brussels, Belgium, RRFM 2009 - 13th Annual Topical Meeting on Research Reactor Fuel Management, Vienna, Austria, 2009-03-22.

APA

Kalcheva, S., Olson, A., Koonen, E., Matos, J., & Beeckmans de West-Meerbeeck, A. (2009). Validation of PLTEMP/ANL V3.6 Code for Evaluation of Safety Margins at the BR2 Reactor. In 13th International Topical Meeting on Research Reactor Fuel Management (RRFM) Brussels, Belgium.

Vancouver

Kalcheva S, Olson A, Koonen E, Matos J, Beeckmans de West-Meerbeeck A. Validation of PLTEMP/ANL V3.6 Code for Evaluation of Safety Margins at the BR2 Reactor. In 13th International Topical Meeting on Research Reactor Fuel Management (RRFM). Brussels, Belgium. 2009

Author

Kalcheva, Silva ; Olson, Arne ; Koonen, Edgar ; Matos, James ; Beeckmans de West-Meerbeeck, André. / Validation of PLTEMP/ANL V3.6 Code for Evaluation of Safety Margins at the BR2 Reactor. 13th International Topical Meeting on Research Reactor Fuel Management (RRFM). Brussels, Belgium, 2009.

Bibtex - Download

@inproceedings{ddac653d361449068fb6458dc2b8b989,
title = "Validation of PLTEMP/ANL V3.6 Code for Evaluation of Safety Margins at the BR2 Reactor",
abstract = "The aim in this paper is to validate the PLTEMP/ANL V3.6 code for thermal hydraulics analysis of the BR2 reactor at steady-state operation under forced flow cooling conditions. Hot channel factors and operation limiting conditions based on selected safety system settings (SSS) with uncertainties were reviewed and included into PLTEMP. Safety margins to ONB (Onset-of-Nucleate-Boiling) and to FI (Flow Instability) are calculated for the BR2 HEU fuelled core and compared with the existing safety limits for the heat fluxes in SAR-BR2. A preliminary thermal-hydraulics analysis is performed for the LEU (UMo) fuel preserving the geometrical parameters of the standard BR2 fuel assembly. Power peaking factors evaluated by MCNP for both HEU and LEU fuel assemblies are included in PLTEMP. Thermal-hydraulics studies are extended to include conditions of natural circulation cooling. The margins to ONB and to FI are estimated for both HEU and LEU cores.",
keywords = "steady state thermal hydraulics analysis, safety margins, hot channel factors",
author = "Silva Kalcheva and Arne Olson and Edgar Koonen and James Matos and {Beeckmans de West-Meerbeeck}, Andr{\'e}",
note = "Score = 3",
year = "2009",
month = "3",
day = "24",
language = "English",
booktitle = "13th International Topical Meeting on Research Reactor Fuel Management (RRFM)",

}

RIS - Download

TY - GEN

T1 - Validation of PLTEMP/ANL V3.6 Code for Evaluation of Safety Margins at the BR2 Reactor

AU - Kalcheva, Silva

AU - Olson, Arne

AU - Koonen, Edgar

AU - Matos, James

A2 - Beeckmans de West-Meerbeeck, André

N1 - Score = 3

PY - 2009/3/24

Y1 - 2009/3/24

N2 - The aim in this paper is to validate the PLTEMP/ANL V3.6 code for thermal hydraulics analysis of the BR2 reactor at steady-state operation under forced flow cooling conditions. Hot channel factors and operation limiting conditions based on selected safety system settings (SSS) with uncertainties were reviewed and included into PLTEMP. Safety margins to ONB (Onset-of-Nucleate-Boiling) and to FI (Flow Instability) are calculated for the BR2 HEU fuelled core and compared with the existing safety limits for the heat fluxes in SAR-BR2. A preliminary thermal-hydraulics analysis is performed for the LEU (UMo) fuel preserving the geometrical parameters of the standard BR2 fuel assembly. Power peaking factors evaluated by MCNP for both HEU and LEU fuel assemblies are included in PLTEMP. Thermal-hydraulics studies are extended to include conditions of natural circulation cooling. The margins to ONB and to FI are estimated for both HEU and LEU cores.

AB - The aim in this paper is to validate the PLTEMP/ANL V3.6 code for thermal hydraulics analysis of the BR2 reactor at steady-state operation under forced flow cooling conditions. Hot channel factors and operation limiting conditions based on selected safety system settings (SSS) with uncertainties were reviewed and included into PLTEMP. Safety margins to ONB (Onset-of-Nucleate-Boiling) and to FI (Flow Instability) are calculated for the BR2 HEU fuelled core and compared with the existing safety limits for the heat fluxes in SAR-BR2. A preliminary thermal-hydraulics analysis is performed for the LEU (UMo) fuel preserving the geometrical parameters of the standard BR2 fuel assembly. Power peaking factors evaluated by MCNP for both HEU and LEU fuel assemblies are included in PLTEMP. Thermal-hydraulics studies are extended to include conditions of natural circulation cooling. The margins to ONB and to FI are estimated for both HEU and LEU cores.

KW - steady state thermal hydraulics analysis

KW - safety margins

KW - hot channel factors

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_103268

UR - http://knowledgecentre.sckcen.be/so2/bibref/6648

M3 - In-proceedings paper

BT - 13th International Topical Meeting on Research Reactor Fuel Management (RRFM)

CY - Brussels, Belgium

ER -

ID: 304583