Next Generation Design Codes for a New Technological Platform for Nuclear Power

Bolshov, L. A.; Mosunova, N. A.; Strizhov, V. F.; Shmidt, O. V.

doi:10.1007/s10512-016-0145-4

Cited by 12 publications

(3 citation statements)

References 10 publications

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“…Compared to earlier publications (Bol'shov et al 2016;Strizhov et al 2017), significant progress should be noted in expanding the applicability areas of codes, the status of their validation and certification in Rostechnadzor. In addition, the codes of new generation package includes the codes for modeling of the installations of the closed nuclear fuel cycle, including 3D multi-component thermohydraulic models, the development of which was started in 2019.…”

Section: The List and Status Of The Codes Of New Generation Developmementioning

confidence: 87%

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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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Section: The List and Status Of The Codes Of New Generation Developmementioning

confidence: 87%

“…General information on "Codes of new generation" project is briefly presented in (Bol'shov et al 2016;Strizhov et al 2017). The purpose of this article is to acquaint the NUCET Journal readers with the latest achievements in this field.…”

Section: Introductionmentioning

confidence: 99%