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1

Tritium and Dust Source Term Estimation for European DEMOnstration Fusion Power Station during Anticipated Transients

Mazzini, Guido, Kaliatka, Tadas, Porfiri, Maria Teresa

Journal:

Journal of Nuclear Engineering and Radiation Science

Year:

2019

Language:

english

File:

PDF, 1.24 MB

english, 2019

2

Modelling of severe accidents in spent fuel pools, analysis of the heat-up of the fuel assemblies in the steam and air environment

Kaliatka, Tadas, Kaliatka, Algirdas, Hohorst, Judy K., Allison, Chris M.

Journal:

Nuclear Engineering and Design

Year:

2018

Language:

english

File:

PDF, 2.50 MB

english, 2018

3

Verification of design characteristics of the RBMK-1500 accident confinement system

E. Ušpuras, A. Kaliatka, K. Almenas

Journal:

Nuclear Engineering and Design

Year:

1995

Language:

english

File:

PDF, 642 KB

english, 1995

4

Validation of coupled neutronic/thermal-hydraulic code RELAP5-3D for RBMK-1500 reactor analysis application

E Uspuras, A Kaliatka, E Bubelis

Journal:

Annals of Nuclear Energy

Year:

2004

Language:

english

File:

PDF, 472 KB

english, 2004

5

Safety analysis of beyond design basis accidents in RBMK-1500 reactors

E. Ušpuras, A. Kaliatka, J. Augutis, S. Rimkevičius, E. Urbonavičius, V. Kopustinskas

Journal:

Annals of Nuclear Energy

Year:

2007

Language:

english

File:

PDF, 426 KB

english, 2007

6

Development and testing of RBMK-1500 model for BDBA analysis employing RELAP/SCDAPSIM code

A. Kaliatka, E. Uspuras

Journal:

Annals of Nuclear Energy

Year:

2008

Language:

english

File:

PDF, 780 KB

english, 2008

7

Analysis of BDBA in RBMK-1500 reactor with long-term loss of heat removal from the core

A. Kaliatka, E. Ušpuras, M. Vaišnoras

Journal:

Annals of Nuclear Energy

Year:

2008

Language:

english

File:

PDF, 1.46 MB

english, 2008

8

Thermal-hydraulic performance of primary system of RBMK in case of accidents

F. D’Auria, B. Gabaraev, V. Radkevitch, A. Moskalev, E. Uspuras, A. Kaliatka, C. Parisi, M. Cherubini, F. Pierro

Journal:

Nuclear Engineering and Design

Year:

2008

Language:

english

File:

PDF, 4.46 MB

english, 2008

9

Analysis of decay heat removal from RBMK-1500 reactor in decommissioning phase by natural circulation of water and air

Algirdas Kaliatka, Eugenijus Uspuras, Mindaugas Vaisnoras, Georgij Krivoshein

Journal:

Nuclear Engineering and Design

Year:

2010

Language:

english

File:

PDF, 1.69 MB

english, 2010

10

Benchmarking analysis of water hammer effects using RELAP5 code and development of RBMK-1500 reactor main circulation circuit model

A. Kaliatka, E. Uspuras, M. Vaisnoras

Journal:

Annals of Nuclear Energy

Year:

2007

Language:

english

File:

PDF, 959 KB

english, 2007

11

Thermal-hydraulic analysis of accidents leading to local coolant flow decrease in the main circulation circuit of RBMK-1500

A Kaliatka, E Uspuras

Journal:

Nuclear Engineering and Design

Year:

2002

Language:

english

File:

PDF, 212 KB

english, 2002

12

Water Hammer Model Sensitivity Study by the FAST Method

Algirdas Kaliatka, Mindaugas Vaisnoras, Eugenijus Uspuras

Journal:

Procedia - Social and Behavioral Sciences

Year:

2010

Language:

english

File:

PDF, 132 KB

english, 2010

13

Simulation of Targets Feeding Pipe Rupture in Wendelstein 7-X Facility Using RELAP5 and COCOSYS Codes

Kaliatka, T., Povilaitis, M., Kaliatka, A., Urbonavicius, E.

Journal:

Journal of Fusion Energy

Year:

2012

Language:

english

File:

PDF, 1012 KB

english, 2012

14

Modeling of pipe break accident in a district heating system using RELAP5 computer code

Kaliatka, A., Valinčius, M.

Journal:

Year:

2012

Language:

english

File:

PDF, 737 KB

english, 2012

15

Experimental Investigation and RELAP5 Modeling of Two-Phase Flow in Horizontal Rectangular Channel

Valinčius, M., Šeporaitis, M., Ušpuras, E., Kaliatka, A.

Journal:

Heat Transfer Engineering

Year:

2011

Language:

english

File:

PDF, 412 KB

english, 2011

16

Heat transfer in the core graphite structures of RBMK nuclear power plants

Knoglinger, E., Wölfl, H., Kaliatka, A.

Journal:

Nuclear Engineering and Design

Year:

2015

Language:

english

File:

PDF, 2.70 MB

english, 2015

17

Integrity control of an RBMK-1500 fuel rod locally oxidized under a bounding reactivity-initiated accident

Boucherit, Hamid, Kaliatka, Algirdas, Lounis, Azzedine

Journal:

Nuclear Science and Techniques

Year:

2019

Language:

english

File:

PDF, 1.41 MB

english, 2019

18

Numerical investigation of two-phase natural convection and temperature stratification phenomena in a rectangular enclosure with conjugate heat transfer

Graževičius, Audrius, Kaliatka, Algirdas, Ušpuras, Eugenijus

Journal:

Nuclear Engineering and Technology

Year:

2019

Language:

english

File:

PDF, 2.91 MB

english, 2019

19

Modeling of void, fast power and graphite temperature reactivity coefficients measurements for the validation of RELAP5-3D RBMK-1500 reactor model

E Uspuras, A Kaliatka, E Bubelis

Journal:

Nuclear Engineering and Design

Year:

2004

Language:

english

File:

PDF, 1.24 MB

english, 2004

20

Development of accident management measures for RBMK-1500 in the case of loss of long-term core cooling

E. Uspuras, A. Kaliatka, V. Vileiniskis

Journal:

Nuclear Engineering and Design

Year:

2006

Language:

english

File:

PDF, 530 KB

english, 2006

21

Specifics of RBMK core cooling in beyond design basis accidents

A. Kaliatka, E. Ušpuras

Journal:

Nuclear Engineering and Design

Year:

2008

Language:

english

File:

PDF, 1.66 MB

english, 2008

22

Integral analysis of large LOCA beyond design basis accident scenario in RBMK-1500

E. Urbonavičius, A. Kaliatka, V. Vileiniškis

Journal:

Nuclear Engineering and Design

Year:

2010

Language:

english

File:

PDF, 3.03 MB

english, 2010

23

Approach to accident management in RBMK-1500

A. Kaliatka, E. Urbonavicius, E. Uspuras

Journal:

Nuclear Engineering and Design

Year:

2008

Language:

english

File:

PDF, 1.11 MB

english, 2008

24

Comparative sensitivity study of the RBMK-1500 reactor one group distribution header blockage accident model

R. Urbonas, A. Kaliatka, V. Kopustinskas

Journal:

Nuclear Engineering and Design

Year:

2010

Language:

english

File:

PDF, 1.20 MB

english, 2010

25

Benchmark analysis of main circulation pump trip events at the Ignalina NPP using RELAP5 code

A Kaliatka, E Uspuras

Journal:

Nuclear Engineering and Design

Year:

2000

Language:

english

File:

PDF, 350 KB

english, 2000

26

Analysis of potential waterhammer at the Ignalina NPP using thermal–hydraulic and structural analysis codes

E Uspuras, A Kaliatka, G Dundulis

Journal:

Nuclear Engineering and Design

Year:

2001

Language:

english

File:

PDF, 262 KB

english, 2001

27

Development and evaluation of additional shutdown system at the Ignalina NPP by employing RELAP5 code

A Kaliatka, E Uspuras

Journal:

Nuclear Engineering and Design

Year:

2002

Language:

english

File:

PDF, 147 KB

english, 2002

28

State-of-the-art computer code RELAP5 validation with RBMK-related separate phenomena data

Rolandas Urbonas, Eugenijus Uspuras, Algirdas Kaliatka

Journal:

Nuclear Engineering and Design

Year:

2003

Language:

english

File:

PDF, 727 KB

english, 2003

29

Thermal–hydraulic evaluation of the RBMK-1500 accident confinement system using CONTAIN 11AF

K Almenas, B Cesna, A Kaliatka, S Rimkevicius, E Uspuras, E Zvinys

Journal:

Nuclear Engineering and Design

Year:

1999

Language:

english

File:

PDF, 435 KB

english, 1999

30

Use of the fast and CSM methods for analyzing uncertainties in hydraulic-shock modeling

E. Uspuras, A. Kaliatka, V. Kopustinskas, M. Vaisnoras

Journal:

Year:

2011

Language:

english

File:

PDF, 438 KB

english, 2011

31

Development of Ignalina NPP RBMK-1500 reactor RELAP5-3D model

E Uspuras, A Kaliatka, E Bubelis

Journal:

Nuclear Engineering and Design

Year:

2003

Language:

english

File:

PDF, 1.04 MB

english, 2003

32

Development of approach for reliability assessment of pipeline network systems

Sigitas Rimkevicius, Algirdas Kaliatka, Mindaugas Valincius, Gintautas Dundulis, Remigijus Janulionis, Albertas Grybenas, Inga Zutautaite

Journal:

Year:

2012

Language:

english

File:

PDF, 1016 KB

english, 2012

33

Analysis of accidents leading to local flow stagnation in parallel fuel channels of RBMK-type reactors

A. Kaliatka, E. Uspuras, M. Vaisnoras

Journal:

Nuclear Engineering and Design

Year:

2011

Language:

english

File:

PDF, 862 KB

english, 2011

34

Sensitivity analysis using contribution to sample variance plot: Application to a water hammer model

S. Tarantola, V. Kopustinskas, R. Bolado-Lavin, A. Kaliatka, E. Ušpuras, M. Vaišnoras

Journal:

Reliability Engineering & System Safety

Year:

2012

Language:

english

File:

PDF, 1.05 MB

english, 2012

35

Uncertainty and sensitivity analysis of MCPs’ trip events at Ignalina NPP

V Vileiniskis, A Kaliatka

Journal:

Nuclear Engineering and Design

Year:

2003

Language:

english

File:

PDF, 241 KB

english, 2003

36

Modelling of valve induced water hammer phenomena in a district heating system

Kaliatka, Algirdas, Vaišnoras, Mindaugas, Valinčius, Mindaugas

Journal:

Computers & Fluids

Year:

2014

Language:

english

File:

PDF, 1.04 MB

english, 2014

37

Analysis of the accident with the coolant discharge into the plasma vessel of the W7-X fusion experimental facility

Ušpuras, E., Kaliatka, A., Kaliatka, T.

Journal:

Fusion Engineering and Design

Year:

2013

Language:

english

File:

PDF, 1.68 MB

english, 2013

38

Synthesis of spent fuel pool accident assessments using severe accident codes

Fleurot, J., Lindholm, I., Kononen, N., Ederli, S., Jaeckel, B., Kaliatka, A., Duspiva, J., Steinbrueck, M., Hollands, T.

Journal:

Annals of Nuclear Energy

Year:

2014

Language:

english

File:

PDF, 3.15 MB

english, 2014

39

The Concept and RELAP5 Model of Thermal-Hydraulic System, Employing a Rapid Condensation for Coolant Circulation

Valinčius, Mindaugas, Šeporaitis, Marijus, Kaliatka, Algirdas, Pabarčius, Raimondas, Gasiūnas, Stasys, Laurinavičius, Darius

Journal:

Heat Transfer Engineering

Year:

2014

Language:

english

File:

PDF, 728 KB

english, 2014

40

Modelling of Water Ingress into Vacuum Vessel Experiments Using RELAP5 Code

Kaliatka, T., Uspuras, E., Kaliatka, A.

Journal:

Journal of Fusion Energy

Year:

2015

Language:

english

File:

PDF, 942 KB

english, 2015

41

Stress-induced Hydride Reorientation and Cracking in Fuel Cladding Tube

GRYBĖNAS, Albertas, MAKAREVIČIUS, Vidas, KALIATKA, Tadas, DUNDULIS, Gintautas, KRIŪKIENĖ, Rita

Journal:

Materials Science (MEDŽIAGOTYRA)

Year:

2014

Language:

english

File:

PDF, 1.46 MB

english, 2014

42

Analysis of the Processes in Spent Fuel Pools in Case of Loss of Heat Removal due to Water Leakage

Kaliatka, Algirdas, Ognerubov, Viktor, Vileiniškis, Virginijus, Ušpuras, Eugenijus

Journal:

Science and Technology of Nuclear Installations

Year:

2013

Language:

english

File:

PDF, 1.11 MB

english, 2013

43

Evaluation of Heat Removal from RBMK-1500 Core Using Control Rods Cooling Circuit

Kaliatka, A., Uspuras, E., Vaisnoras, M.

Journal:

Science and Technology of Nuclear Installations

Year:

2008

Language:

english

File:

PDF, 772 KB

english, 2008

44

Modelling of QUENCH-03 and QUENCH-06 Experiments Using RELAP/SCDAPSIM and ASTEC Codes

Kaliatka, Tadas, Kaliatka, Algirdas, Vileiniškis, Virginijus, Ušpuras, Eugenijus

Journal:

Science and Technology of Nuclear Installations

Year:

2014

Language:

english

File:

PDF, 1.78 MB

english, 2014

45

Modelling of pressure increase protection system for the vacuum vessel of W7-X device

Kaliatka, Tadas, Uspuras, Eugenijus, Kaliatka, Algirdas

Journal:

Fusion Engineering and Design

Year:

2016

Language:

english

File:

PDF, 841 KB

english, 2016

46

Application of Best Estimate Approach for Modelling of QUENCH-03 and QUENCH-06 Experiments

Kaliatka, Tadas, Kaliatka, Algirdas, Vileiniskis, Virginijus

Journal:

Nuclear Engineering and Technology

Year:

2016

Language:

english

File:

PDF, 1.78 MB

english, 2016

47

SARGEN-IV: Consideration on the possible content of the safety analysis report for innovative ESNII reactors

Ammirabile, L., Tuček, K., Blanc, D., Pabarcius, R., Kaliatka, A., Mansani, L., Carluec, B., Dufour, P., Homann, C.

Journal:

Nuclear Engineering and Design

Year:

2016

Language:

english

File:

PDF, 1.05 MB

english, 2016

48

Analysis of processes in RBMK-1500 fuel rods during the operation, short and intermediate term storage

Kaliatka, T., Kaliatka, A., Makarevicius, V.

Journal:

Year:

2014

File:

PDF, 572 KB

2014

49

Best estimate analysis of PHEBUS FPT1 experiment bundle phase using ASTEC code ICARE module

Vileiniskis, V., Kaliatka, A.

Journal:

Year:

2011

Language:

english

File:

PDF, 729 KB

english, 2011

50

Development of RBMK-1500 Model for BDBA Analysis Using RELAP/SCDAPSIM Code

USPURAS, Eugenijus, KALIATKA, Algirdas

Journal:

Journal of Power and Energy Systems

Year:

2008

Language:

english

File:

PDF, 430 KB

english, 2008

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