3D EVKLID/V2 Code Aided Simulation of Severe Accidents

Usov, E. V.; Butov, A. A.; Chukhno, V. I.; Klimonov, I. A.; Kudashov, I. G.; Zhdanov, V. S.; Прибатурин, Н. А.; Mosunova, N. A.; Strizhov, V. F.

doi:10.1007/s10512-019-00575-5

Cited by 5 publications

(1 citation statement)

References 15 publications

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“…The EUCLID/V2 3 code is designed to analyze and justify the safety of NPPs with fast neutron reactors with liquid metal coolants in the normal and abnormal operation modes, including accidents, severe ones as well (Usov et al 2018a(Usov et al , 2018bButov et al 2019aButov et al , 2019b. It is based on the first version of the code EUCLID/V1 (detailed information about which can be found in (Mosunova 2018;Alipchenkov et al 2018)) and includes all of its models.…”

Section: Brief Informationmentioning

confidence: 99%

Codes of new generation for safety justification of power units with a closed nuclear fuel cycle developed for the “PRORYV” project

Bolshov¹,

Strizhov²,

Mosunova³

2020

NUCET

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The article describes the status of development of codes of new generation for the “PRORYV” Project by the end of 2019: twenty-five commercial-grade software products to justify design solutions and safety of power units with fast neutron reactors and liquid metal coolant (sodium and lead) in a closed nuclear fuel cycle. The developed system of codes is multi-physical and multi-scale that allows performing both calculations of the whole installations and high precision calculations of their individual elements. The developed codes offer unique features. Twelve developed codes have already been certified by Rostechnadzor, and six more have been submitted for certification. In addition to creating the software products, a large-scale work is being carried out to conduct experimental studies for code validation that meet modern requirements imposed by the codes: unique measurement techniques have been created; experimental data on flow characteristics of heavy liquid metal coolant (HLMC) in a fuel assembly simulator have been obtained, as well as of “gas-HLMC” interphase interaction after inert gas injection in HLMC and characteristics of heat exchange between the inert gas and HLMC. The results are already used for validation of system and CFD codes used in the “PRORYV” Project.

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