Fuel Pin Melting in a Fast Reactor and Melt Solidification: Simulation Using the SAFR/V1 Module of the EVKLID/V2 Integral Code

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/s10512-018-0389-2

Cited by 20 publications

(5 citation statements)

References 1 publication

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“…Simulation methods were developed to simulate severe accidents with core degradation in fast reactors with different fuel types (oxide, metallic and nitride) and different liquid metal coolant (sodium and lead). These methods were implemented in the SAFR module [2][3][4], being the part of the EUCLID/V2 coupled code [1]. To simulate melt relocation the system of the mass, energy and momentum equation is used:…”

Section: The Basic Model To Simulate Thermal Destruction Of the Fuel Pinmentioning

confidence: 99%

“…Using the software module for calculating the destruction of fuel pins [2][3][4], calculations were carried out for two different energy release: uniform along the fuel length and non-uniform (sin(x)law).…”

Section: Fuel Pin Modelmentioning

confidence: 99%

“…To analyze the processes of destruction of the core elements of promising reactors, a universal design code is being developed [1], which includes a module for calculating the destruction of the core and fuel elements (fuel elements) [2][3][4].…”

Section: Introductionmentioning

confidence: 99%

“…The module for calculating the destruction of fuel elements is intended for calculating the problems of modeling the melting of fuel elements in fast reactors. The problem of thermal destruction of a fuel element is complex; to simplify calculations, it is divided into two subtasks: the thermal problem during melting / solidification and the problem of dripping over the surface of a fuel element [2,4].…”

Section: Introductionmentioning

confidence: 99%

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Analysis of different factors on the features of thermal destruction of a fuel pin

Usov

Saikina

Chuhno

2021

J. Phys.: Conf. Ser.

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The presented work studies the influence of various factors that affect the specific features of fuel pins melting. For this purpose, fuel pins with different geometries and energy release are considered. Numerical simulation of melting is carried out using a program module for calculating the destruction of fuel rods. Comparison with theoretical calculations is made. The analysis of the convergence of calculations with respect to the time step value and the number of calculated cells along the radius and height is carried out. As a result of work with the use of numerical methods, the characteristic times of destruction of fuel elements during an accident with a loss of coolant flow rate (an accident of the ULOF type) and the dependence of weight loss on time are obtained under various conditions.

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Section: The Basic Model To Simulate Thermal Destruction Of the Fuel Pinmentioning

confidence: 99%

Section: Fuel Pin Modelmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Analysis of different factors on the features of thermal destruction of a fuel pin

Usov

Saikina

Chuhno

2021

J. Phys.: Conf. Ser.

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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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Experiment-Based Verification of the SAFR/V1 Module of the EVKLID/V2 Integral Code for Thermal Breakdown of Fuel Pins in a Fast Reactor

et al. 2018

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Fuel Pin Melting in a Fast Reactor and Melt Solidification: Simulation Using the SAFR/V1 Module of the EVKLID/V2 Integral Code

Cited by 20 publications

References 1 publication

Analysis of different factors on the features of thermal destruction of a fuel pin

Analysis of different factors on the features of thermal destruction of a fuel pin

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

Experiment-Based Verification of the SAFR/V1 Module of the EVKLID/V2 Integral Code for Thermal Breakdown of Fuel Pins in a Fast Reactor

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