Verification and Validation of the EUCLID/V2 Integrated Code's HEFEST-FR Module.

Authors: Tsaun, S. V., Butov, A. A., Klimonov, I. A., Moiseenko, E. V., Mosunova, N. A., Strizhov, V. F., Usov, E. V., Chukhno, V. I.

Source: Thermal Engineering; Dec2024, Vol. 71 Issue 12, p1083-1093, 11p

Automatic Time Step Selection for Numerical Solution of Neutron Diffusion Problems
Finite difference methods: theory and applications (International conference)

Authors: Avvakumov, A. V., Strizhov, V. F., Vabishchevich, P. N., Vasilev, A. O.

Source: Lecture notes in computer science. 11386:145-152

Availability: http://explore.bl.uk/primo_library/libweb/action/display.do?tabs=detailsTab&gathStatTab=true&ct=display&fn=search&doc=ETOCCN604792524&indx=1&recIds=ETOCCN604792524

Elaboration of a Phenomena Identification Ranking Table (PIRT) for the modelling of In-Vessel Retention

Authors: Fichot, F., Carénini, L., Bakouta, N., Esmaili, H., Humphries, L., Laato, T., Le Tellier, R., Saas, L., Melnikov, I., Pandazis, P., Weber, S., Park, R.J., Filippov, A., Strizhov, V.

Source: In Annals of Nuclear Energy October 2020 146

Solution of the 3D Neutron Diffusion Benchmark by FEM
Large-scale scientific computing (International conference)

Authors: Avvakumov, A. V., Vabishchevich, P. N., Vasilev, A. O., Strizhov, V. F.

Source: Lecture notes in computer science. 10665:435-442

Availability: http://explore.bl.uk/primo_library/libweb/action/display.do?tabs=detailsTab&gathStatTab=true&ct=display&fn=search&doc=ETOCCN603074772&indx=1&recIds=ETOCCN603074772

Algorithms for Numerical Simulation of Non-stationary Neutron Diffusion Problems
Numerical analysis and its applications (International conference)

Authors: Avvakumov, A. V., Strizhov, V. F., Vabishchevich, P. N., Vasilev, A. O.

Source: Lecture notes in computer science. 10187:212-219

Availability: http://explore.bl.uk/primo_library/libweb/action/display.do?tabs=detailsTab&gathStatTab=true&ct=display&fn=search&doc=ETOCCN602340697&indx=1&recIds=ETOCCN602340697

3D EVKLID/V2 Code Aided Simulation of Severe Accidents

Authors: Usov, E. V., Butov, A. A., Chukhno, V. I., Klimonov, I. A., Kudashov, I. G., Zhdanov, V. S., Pribaturin, N. A., Mosunova, N. A., Strizhov, V. F.

Source: Atomic energy. 127(1):1-7

Availability: http://explore.bl.uk/primo_library/libweb/action/display.do?tabs=detailsTab&gathStatTab=true&ct=display&fn=search&doc=ETOCvdc_100141595827.0x000001&indx=1&recIds=ETOCvdc_100141595827.0x000001

The EUCLID/V2 Code Physical Models for Calculating Fuel Rod and Core Failures in a Liquid Metal Cooled Reactor

Authors: Butov, A. A., Zhdanov, V. S., Klimonov, I. A., Kudashov, I. G., Kutlimetov, A. E., Mosunova, N. A., Strizhov, V. F., Sorokin, A. A., Frolov, S. A., Usov, E. V., Chukhno, V. I.

Source: Thermal engineering. 66(5):293-301

Availability: http://explore.bl.uk/primo_library/libweb/action/display.do?tabs=detailsTab&gathStatTab=true&ct=display&fn=search&doc=ETOCvdc_100125438321.0x000001&indx=1&recIds=ETOCvdc_100125438321.0x000001

Verification of the EUCLID/V2 Code Based on Experiments Involving Destruction of a Liquid Metal Cooled Reactor's Core Components

Authors: Butov, A. A., Zhdanov, V. S., Klimonov, I. A., Kudashov, I. G., Kutlimetov, A. E., Lobanov, P. D., Mosunova, N. A., Sorokin, A. A., Strizhov, V. F., Usov, E. V., Chukhno, V. I.

Source: Thermal engineering. 66(5):302-309

Availability: http://explore.bl.uk/primo_library/libweb/action/display.do?tabs=detailsTab&gathStatTab=true&ct=display&fn=search&doc=ETOCvdc_100124809146.0x000001&indx=1&recIds=ETOCvdc_100124809146.0x000001

SAFR/V1 (EVKLID/V2 Integral Code Module) Aided Simulation of Melt Movement Along the Surface of a Fuel Element in a Fast Reactor During a Serious Accident

Authors: Usov, E. V., Butov, A. A., Chukhno, V. I., Klimonov, I. A., Kudashov, I. G., Zhdanov, V. S., Pribaturin, N. A., Mosunova, N. A., Strizhov, V. F.

Source: Atomic energy. 124(4):232-237

Availability: http://explore.bl.uk/primo_library/libweb/action/display.do?tabs=detailsTab&gathStatTab=true&ct=display&fn=search&doc=ETOCvdc_100141595724.0x000001&indx=1&recIds=ETOCvdc_100141595724.0x000001

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

Authors: Usov, E. V., Butov, A. A., Chukhno, V. I., Klimonov, I. A., Kudashov, I. G., Zhdanov, V. S., Pribaturin, N. A., Mosunova, N. A., Strizhov, V. F.

Source: Atomic energy. 124(3):147-153

Availability: http://explore.bl.uk/primo_library/libweb/action/display.do?tabs=detailsTab&gathStatTab=true&ct=display&fn=search&doc=ETOCvdc_100141595713.0x000001&indx=1&recIds=ETOCvdc_100141595713.0x000001

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

Authors: Usov, E. V., Butov, A. A., Chukhno, V. I., Klimonov, I. A., Kudashov, I. G., Zhdanov, V. S., Pribaturin, N. A., Mosunova, N. A., Strizhov, V. F.

Source: Atomic energy. 124(5):287-291

Availability: http://explore.bl.uk/primo_library/libweb/action/display.do?tabs=detailsTab&gathStatTab=true&ct=display&fn=search&doc=ETOCvdc_100140852254.0x000001&indx=1&recIds=ETOCvdc_100140852254.0x000001

The EUCLID/V1 Integrated Code for Safety Assessment of Liquid Metal Cooled Fast Reactors. Part 2: Validation and Verification

Authors: Alipchenkov, V. M., Boldyrev, A. V., Veprev, D. P., Zeigarnik, Yu. A., Kolobaeva, P. V., Moiseenko, E. V., Mosunova, N. A., Seleznev, E. F., Strizhov, V. F., Usov, E. V., Osipov, S. L., Gorbunov, V. S., Afremov, D. A., Semchenkov, A. A.

Source: Thermal engineering. 65(9):627-640

Availability: http://explore.bl.uk/primo_library/libweb/action/display.do?tabs=detailsTab&gathStatTab=true&ct=display&fn=search&doc=ETOCvdc_100151170278.0x000001&indx=1&recIds=ETOCvdc_100151170278.0x000001

Validation of the severe accident module of the EVKLID/V2 integral code on the base of experiments with fission products release and dissociation of nitride fuel.

Authors: Zhdanov, V. S., Klimonov, I. A., Kudashov, I. G., Mosunova, N. A., Strizhov, V. F., Sycheva, T. V., Usov, E. V., Chukhno, V. I., Kireev, G. A., Krivov, M. P., Skupov, M. V.

Source: Atomic Energy; Mar2024, Vol. 135 Issue 5/6, p297-301, 5p

Subject Terms: FISSION products, FAST reactors, LIQUID metals, FAST neutrons, NITRIDES

Experimental investigation of the impulse gas injection into liquid and the use of experimental data for verification of the HYDRA-IBRAE/LM thermohydraulic code

Authors: Lobanov, P. D., Usov, E. V., Butov, A. A., Pribaturin, N. A., Mosunova, N. A., Strizhov, V. F., Chukhno, V. I., Kutlimetov, A. E.

Source: THERMAL ENGINEERING C/C OF TEPLOENERGETIKA. 64(10):770-776

Availability: http://explore.bl.uk/primo_library/libweb/action/display.do?tabs=detailsTab&gathStatTab=true&ct=display&fn=search&doc=ETOCRN385705096&indx=1&recIds=ETOCRN385705096

Selecting an optimal model for forecasting the volumes of railway goods transportation

Authors: Rudakov, K. V., Strizhov, V. V., Kashirin, D. O., Kuznetsov, M. P., Motrenko, A. P., Stenina, M. M.

Source: AUTOMATION AND REMOTE CONTROL C/C OF AVTOMATIKA I TELEMEKHANIKA. 78(1):75-87

Availability: http://explore.bl.uk/primo_library/libweb/action/display.do?tabs=detailsTab&gathStatTab=true&ct=display&fn=search&doc=ETOCRN382418310&indx=1&recIds=ETOCRN382418310

HYDRA-IBRAE/LM/V1 Thermohydraulic Code Verification Based on BN-600 Experiments

Authors: Klimonov, I. A., Usov, E. V., Dugarov, G. A., Butov, A. A., Kudashov, I. G., Ivanov, E. N., Mosunova, N. A., Strizhov, V. F., Anfimov, A. M., Gorbunov, V. S.

Source: ATOMIC ENERGY -NEW YORK- C/C OF ATOMNAIA ENERGIIA. 122(5):311-318

Availability: http://explore.bl.uk/primo_library/libweb/action/display.do?tabs=detailsTab&gathStatTab=true&ct=display&fn=search&doc=ETOCRN385479425&indx=1&recIds=ETOCRN385479425

ICONE17-75205 Molten Pool Models Validation and Cross-Verification: CFD and SOCRAT Code
Nuclear engineering

Authors: Filippov, A., Strizhov, V., Tarasov, O.

Source: ICONE - PROCEEDINGS. 3:223-232

Availability: http://explore.bl.uk/primo_library/libweb/action/display.do?tabs=detailsTab&gathStatTab=true&ct=display&fn=search&doc=ETOCCN075723993&indx=1&recIds=ETOCCN075723993

ICONE17-75203 Simulation of Vessel-With-Melt Deformation by SOCRAT/HEFEST Code
Nuclear engineering

Authors: Filippov, A., Drobyshevsky, N., Kiselev, A., Strizhov, V.

Source: ICONE - PROCEEDINGS. 2:53-60

Availability: http://explore.bl.uk/primo_library/libweb/action/display.do?tabs=detailsTab&gathStatTab=true&ct=display&fn=search&doc=ETOCCN075722575&indx=1&recIds=ETOCCN075722575

ICONE14-89457 Debris Thermal Hydraulics Modeling of QUENCH Experiments
Nuclear engineering; ICONE 14

Authors: Kisselev, A. E., Kobelev, G. V., Strizhov, V. F., Vasiliev, A. D.

Source: ICONE -PROCEEDINGS-. CONF 14:477-488

Availability: http://explore.bl.uk/primo_library/libweb/action/display.do?tabs=detailsTab&gathStatTab=true&ct=display&fn=search&doc=ETOCCN063649117&indx=1&recIds=ETOCCN063649117

ICONE14-89296 Best Estimate Methodology for Modeling Bubble Flows
Nuclear engineering; ICONE 14

Authors: Bolshov, L. A., Chudanov, V. V., Strizhov, V. F., Alekseenko, S. V., Meledin, V. G., Pribaturin, N. A.

Source: ICONE -PROCEEDINGS-. CONF 14:317-328

Availability: http://explore.bl.uk/primo_library/libweb/action/display.do?tabs=detailsTab&gathStatTab=true&ct=display&fn=search&doc=ETOCCN063648927&indx=1&recIds=ETOCCN063648927