Application of PARET/V7.5 for the Transient Analysis of the BR2 Reactor: Reactivity Insertion Transients with Automatic Power Reduction by the Control Rods

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Application of PARET/V7.5 for the Transient Analysis of the BR2 Reactor: Reactivity Insertion Transients with Automatic Power Reduction by the Control Rods. / Kalcheva, Silva; Koonen, Edgar; Olson, Arne; Matos, James; Beeckmans de West-Meerbeeck, André (Peer reviewer).

2009 International Meeting on Reduced Enrichment for Research and Test Reactors. Illinois, United States, 2009.

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

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Kalcheva, S, Koonen, E, Olson, A, Matos, J & Beeckmans de West-Meerbeeck, A 2009, Application of PARET/V7.5 for the Transient Analysis of the BR2 Reactor: Reactivity Insertion Transients with Automatic Power Reduction by the Control Rods. in 2009 International Meeting on Reduced Enrichment for Research and Test Reactors. Illinois, United States, RERTR 2009, Beijing, China, 2009-11-01.

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@inproceedings{eb58e4a3bf884f559a185b9f89a6c06f,
title = "Application of PARET/V7.5 for the Transient Analysis of the BR2 Reactor: Reactivity Insertion Transients with Automatic Power Reduction by the Control Rods",
abstract = "This paper presents the first part of the transient analysis for the BR2 reactor, performed with the ANL – transient thermal-hydraulics code PARET/V7.5. Considered are reactivity insertion transients with automatic power reduction by the control rods. The code qualification for application at BR2 is performed against existing transient analysis data for standard HEU fuel (93{\%} U5) and assuming zero reactivity coefficients, as it is done in the SAR-BR2. Calculations at reactor manipulation conditions and during nominal power operation are performed for variable initial flow. Time variations of power, energy, coolant and clad/fuel temperature are evaluated and analyzed. The admissible reactivity insertion rate is determined in each specific case. The sensitivity of the results to variation of the delay time for the response of the control system to a power trip is considered. After comparison of the results obtained for the HEU core with the safety limits in the SAR-BR2, the PARET/V7.5 code is used for simulation of the described transients in the LEU core, loaded with dispersed U-9Mo fuel (20{\%} U5, 7.5-8.0 gUtot/cc).",
keywords = "reactivity insertion transients",
author = "Silva Kalcheva and Edgar Koonen and Arne Olson and James Matos and {Beeckmans de West-Meerbeeck}, Andr{\'e}",
note = "Score = 3",
year = "2009",
month = "11",
day = "4",
language = "English",
booktitle = "2009 International Meeting on Reduced Enrichment for Research and Test Reactors",

}

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TY - GEN

T1 - Application of PARET/V7.5 for the Transient Analysis of the BR2 Reactor: Reactivity Insertion Transients with Automatic Power Reduction by the Control Rods

AU - Kalcheva, Silva

AU - Koonen, Edgar

AU - Olson, Arne

AU - Matos, James

A2 - Beeckmans de West-Meerbeeck, André

N1 - Score = 3

PY - 2009/11/4

Y1 - 2009/11/4

N2 - This paper presents the first part of the transient analysis for the BR2 reactor, performed with the ANL – transient thermal-hydraulics code PARET/V7.5. Considered are reactivity insertion transients with automatic power reduction by the control rods. The code qualification for application at BR2 is performed against existing transient analysis data for standard HEU fuel (93% U5) and assuming zero reactivity coefficients, as it is done in the SAR-BR2. Calculations at reactor manipulation conditions and during nominal power operation are performed for variable initial flow. Time variations of power, energy, coolant and clad/fuel temperature are evaluated and analyzed. The admissible reactivity insertion rate is determined in each specific case. The sensitivity of the results to variation of the delay time for the response of the control system to a power trip is considered. After comparison of the results obtained for the HEU core with the safety limits in the SAR-BR2, the PARET/V7.5 code is used for simulation of the described transients in the LEU core, loaded with dispersed U-9Mo fuel (20% U5, 7.5-8.0 gUtot/cc).

AB - This paper presents the first part of the transient analysis for the BR2 reactor, performed with the ANL – transient thermal-hydraulics code PARET/V7.5. Considered are reactivity insertion transients with automatic power reduction by the control rods. The code qualification for application at BR2 is performed against existing transient analysis data for standard HEU fuel (93% U5) and assuming zero reactivity coefficients, as it is done in the SAR-BR2. Calculations at reactor manipulation conditions and during nominal power operation are performed for variable initial flow. Time variations of power, energy, coolant and clad/fuel temperature are evaluated and analyzed. The admissible reactivity insertion rate is determined in each specific case. The sensitivity of the results to variation of the delay time for the response of the control system to a power trip is considered. After comparison of the results obtained for the HEU core with the safety limits in the SAR-BR2, the PARET/V7.5 code is used for simulation of the described transients in the LEU core, loaded with dispersed U-9Mo fuel (20% U5, 7.5-8.0 gUtot/cc).

KW - reactivity insertion transients

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_103272

UR - http://knowledgecentre.sckcen.be/so2/bibref/6652

M3 - In-proceedings paper

BT - 2009 International Meeting on Reduced Enrichment for Research and Test Reactors

CY - Illinois, United States

ER -

ID: 69376