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

Tuunanen, Jari; Vihavainen, Juhani; D'Auria, Francesco Saverio; Frogheri, M; Galassi, G. M.; Kimber, G.R.; Lillington, J.N.; Alien, Elizabeth; Williams, Timothy

doi:10.1016/s0029-5493(99)00312-x

Cited by 17 publications

(3 citation statements)

References 2 publications

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“…The Reactor Excursion and Leak Analysis Program (RELAP5) is a best-estimate nuclear system code; it was developed at Idaho National Engineering Laboratory (INEL) at the request of the US Nuclear Regulatory Commission (NRC) [15]. It is mainly used for the transients' analysis of light-water reactor (LWR); however, the generalization of the RELAP5 code allowed its application to the nuclear and nonnuclear fields [1,4,11]. It has been designed to simulate the thermal-hydraulic behavior of installations during accidental or incidental transients.…”

Section: Relap5/mod32 Code Presentationmentioning

confidence: 99%

“…The power plants' safety is largely based on simulation [5]. Nowadays, the bestestimate nuclear system codes such as TRAC [6], RETRAN [7], RELAP5 [8,12], ATHLET [9], CATHARE [10], and APROS [11] are widely used to investigate the thermal-hydraulic characteristics of nuclear power plants either during steady-state operation or accidental transients and simulate the overall behavior of the installation (pumps, piping, heat exchangers, tanks, valves, control loops, etc. ).…”

Section: Introductionmentioning

confidence: 99%

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Numerical Simulation of the Accidental Transient of an Industrial Steam Boiler

Cheridi¹,

Chaker²,

Loubar³

2019

Heat and Mass Transfer - Advances in Science and Technology Applications

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Numerical simulation allows a better understanding of thermal-hydraulic phenomena that can take place in thermal installations. It is a capital contribution, especially in accident situations. The code RELAP5/Mod3.2 makes it possible to predict the thermal-hydraulic behavior of these installations during the normal and accidental operations. The present chapter focuses on accidental transient modeling and simulation of an industrial steam boiler by the code RELAP5/Mod3.2. This steam boiler is radiant type, high power, natural circulation, and a single drum. The model of the boiler developed for the RELAP5/Mod3.2 code encompasses the entire installation. The control loop of the water level in the steam drum and the superheated steam temperature are also included in the model. The qualification process of the steam boiler model is based on the steam boiler operation data under steady-state operating conditions. The comparative study shows that the theoretical results of the code RELAP5 are in good agreement with the operating data of the installation. To evaluate the behavior and response of the boiler in accident situations, the loss of feedwater following pump power loss, with and without protective operations, was simulated.

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Section: Relap5/mod32 Code Presentationmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Numerical Simulation of the Accidental Transient of an Industrial Steam Boiler

Cheridi¹,

Chaker²,

Loubar³

2019

Heat and Mass Transfer - Advances in Science and Technology Applications

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“…They reported that the effect of the hole pattern such as a staggered and parallel type is relatively smaller than that of p/d, and the dominant frequency of the pressure oscillation increases with p/d. Tuunanen et al [2] experimentally studied the performance of CMT of advanced light water reactors in small break LOCA conditions, and they demonstrated the importance of a flow distributor in the CMT to limit a rapid condensation. The optimal design of the flow distributor is very important to ensure the structural integrity of the reactor system and their safe operation during some transient or accident conditions.…”

Section: Introductionmentioning

confidence: 99%

Numerical studies on the performance of a flow distributor in tank

Shin

Kim

Ryu

et al. 2015

AIP Conference Proceedings

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Flow distributors are generally observed in several nuclear power plants. During core make-up tank (CMT) injection into the reactor, the condensation and thermal stratification are observed in the CMT, and rapid condensation disturbs the injection operation. To reduce the condensation phenomena in the tank, CMT was equipped with a flow distributor. The optimal design of the flow distributor is very important to ensure the structural integrity the CMT and its safe operation during certain transient or accident conditions. In the present study, we numerically investigated the performance of a flow distributor in tank with different shape factors such as the total number of holes, pitch-to-hole diameter ratios, diameter of the hole, and the area ratios. These data will contribute to a design of the flow distributor.

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References

2024

Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors

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

Cited by 17 publications

References 2 publications

Numerical Simulation of the Accidental Transient of an Industrial Steam Boiler

Numerical Simulation of the Accidental Transient of an Industrial Steam Boiler

Numerical studies on the performance of a flow distributor in tank

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