Analyses of PACTEL passive safety injection experiments with APROS, CATHARE and RELAP5 codes

Jari Tuunanen (Corresponding Author), Juhani Vihavainen, Francesco D'Auria, Monica Frogheri, G.M Galassi, George Kimber, John Lillington, Elizabeth Alien, T.G Williams

Research output: Contribution to journalArticleScientificpeer-review

13 Citations (Scopus)

Abstract

The European Commission fourth framework programme project ‘Assessment of passive safety injection systems of advanced light water reactors’ involved experiments on the PACTEL test facility and computer simulations of selected experiments. The experiments focused on the performance of passive safety injection systems (PSIS) of advanced light water reactors (ALWRs) in small break loss-of-coolant accident (SBLOCA) conditions. The PSIS consisted of a core make-up tank (CMT) and two pipelines. A pressure balancing line (PBL) connected the CMT to one cold leg. The injection line (IL) connected it to the downcomer. The project involved 15 experiments in three series. The experiments provided information about condensation and heat transfer processes in the CMT, thermal stratification of water in the CMT, and natural circulation flow through the PSIS lines. The project included validation of three thermal-hydraulic computer codes (APROS, CATHARE and RELAP5). The analyses showed the codes are capable of simulating the overall behaviour of the transients. The codes predicted accurately the core heatup, which occurred when the primary coolant inventory was reduced so much that the core top became free of water. The detailed analyses of the calculation results showed that some models in the codes still need improvements. Especially, further development of models for thermal stratification, condensation and natural circulation flow with small driving forces would be necessary for accurate simulation of the phenomena in the PSIS.
Original languageEnglish
Pages (from-to)261 - 286
Number of pages26
JournalNuclear Engineering and Design
Volume198
Issue number3
DOIs
Publication statusPublished - 2000
MoE publication typeA1 Journal article-refereed

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safety
injection
Thermal stratification
Light water reactors
light water reactors
experiment
Experiments
condensation
Condensation
stratification
project assessment
water
Loss of coolant accidents
loss of coolant
Water
European Commission
Test facilities
Coolants
computer simulation
coolants

Cite this

Tuunanen, J., Vihavainen, J., D'Auria, F., Frogheri, M., Galassi, G. M., Kimber, G., ... Williams, T. G. (2000). Analyses of PACTEL passive safety injection experiments with APROS, CATHARE and RELAP5 codes. Nuclear Engineering and Design, 198(3), 261 - 286. https://doi.org/10.1016/S0029-5493(99)00312-X
Tuunanen, Jari ; Vihavainen, Juhani ; D'Auria, Francesco ; Frogheri, Monica ; Galassi, G.M ; Kimber, George ; Lillington, John ; Alien, Elizabeth ; Williams, T.G. / Analyses of PACTEL passive safety injection experiments with APROS, CATHARE and RELAP5 codes. In: Nuclear Engineering and Design. 2000 ; Vol. 198, No. 3. pp. 261 - 286.
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abstract = "The European Commission fourth framework programme project ‘Assessment of passive safety injection systems of advanced light water reactors’ involved experiments on the PACTEL test facility and computer simulations of selected experiments. The experiments focused on the performance of passive safety injection systems (PSIS) of advanced light water reactors (ALWRs) in small break loss-of-coolant accident (SBLOCA) conditions. The PSIS consisted of a core make-up tank (CMT) and two pipelines. A pressure balancing line (PBL) connected the CMT to one cold leg. The injection line (IL) connected it to the downcomer. The project involved 15 experiments in three series. The experiments provided information about condensation and heat transfer processes in the CMT, thermal stratification of water in the CMT, and natural circulation flow through the PSIS lines. The project included validation of three thermal-hydraulic computer codes (APROS, CATHARE and RELAP5). The analyses showed the codes are capable of simulating the overall behaviour of the transients. The codes predicted accurately the core heatup, which occurred when the primary coolant inventory was reduced so much that the core top became free of water. The detailed analyses of the calculation results showed that some models in the codes still need improvements. Especially, further development of models for thermal stratification, condensation and natural circulation flow with small driving forces would be necessary for accurate simulation of the phenomena in the PSIS.",
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Tuunanen, J, Vihavainen, J, D'Auria, F, Frogheri, M, Galassi, GM, Kimber, G, Lillington, J, Alien, E & Williams, TG 2000, 'Analyses of PACTEL passive safety injection experiments with APROS, CATHARE and RELAP5 codes', Nuclear Engineering and Design, vol. 198, no. 3, pp. 261 - 286. https://doi.org/10.1016/S0029-5493(99)00312-X

Analyses of PACTEL passive safety injection experiments with APROS, CATHARE and RELAP5 codes. / Tuunanen, Jari (Corresponding Author); Vihavainen, Juhani; D'Auria, Francesco; Frogheri, Monica; Galassi, G.M; Kimber, George; Lillington, John; Alien, Elizabeth; Williams, T.G.

In: Nuclear Engineering and Design, Vol. 198, No. 3, 2000, p. 261 - 286.

Research output: Contribution to journalArticleScientificpeer-review

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T1 - Analyses of PACTEL passive safety injection experiments with APROS, CATHARE and RELAP5 codes

AU - Tuunanen, Jari

AU - Vihavainen, Juhani

AU - D'Auria, Francesco

AU - Frogheri, Monica

AU - Galassi, G.M

AU - Kimber, George

AU - Lillington, John

AU - Alien, Elizabeth

AU - Williams, T.G

PY - 2000

Y1 - 2000

N2 - The European Commission fourth framework programme project ‘Assessment of passive safety injection systems of advanced light water reactors’ involved experiments on the PACTEL test facility and computer simulations of selected experiments. The experiments focused on the performance of passive safety injection systems (PSIS) of advanced light water reactors (ALWRs) in small break loss-of-coolant accident (SBLOCA) conditions. The PSIS consisted of a core make-up tank (CMT) and two pipelines. A pressure balancing line (PBL) connected the CMT to one cold leg. The injection line (IL) connected it to the downcomer. The project involved 15 experiments in three series. The experiments provided information about condensation and heat transfer processes in the CMT, thermal stratification of water in the CMT, and natural circulation flow through the PSIS lines. The project included validation of three thermal-hydraulic computer codes (APROS, CATHARE and RELAP5). The analyses showed the codes are capable of simulating the overall behaviour of the transients. The codes predicted accurately the core heatup, which occurred when the primary coolant inventory was reduced so much that the core top became free of water. The detailed analyses of the calculation results showed that some models in the codes still need improvements. Especially, further development of models for thermal stratification, condensation and natural circulation flow with small driving forces would be necessary for accurate simulation of the phenomena in the PSIS.

AB - The European Commission fourth framework programme project ‘Assessment of passive safety injection systems of advanced light water reactors’ involved experiments on the PACTEL test facility and computer simulations of selected experiments. The experiments focused on the performance of passive safety injection systems (PSIS) of advanced light water reactors (ALWRs) in small break loss-of-coolant accident (SBLOCA) conditions. The PSIS consisted of a core make-up tank (CMT) and two pipelines. A pressure balancing line (PBL) connected the CMT to one cold leg. The injection line (IL) connected it to the downcomer. The project involved 15 experiments in three series. The experiments provided information about condensation and heat transfer processes in the CMT, thermal stratification of water in the CMT, and natural circulation flow through the PSIS lines. The project included validation of three thermal-hydraulic computer codes (APROS, CATHARE and RELAP5). The analyses showed the codes are capable of simulating the overall behaviour of the transients. The codes predicted accurately the core heatup, which occurred when the primary coolant inventory was reduced so much that the core top became free of water. The detailed analyses of the calculation results showed that some models in the codes still need improvements. Especially, further development of models for thermal stratification, condensation and natural circulation flow with small driving forces would be necessary for accurate simulation of the phenomena in the PSIS.

U2 - 10.1016/S0029-5493(99)00312-X

DO - 10.1016/S0029-5493(99)00312-X

M3 - Article

VL - 198

SP - 261

EP - 286

JO - Nuclear Engineering and Design

JF - Nuclear Engineering and Design

SN - 0029-5493

IS - 3

ER -