A. Kaliatka: search on Z-Library

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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

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

4

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

5

Heat removal from RBMK reactor core using non-regular means

Kaliatka, Algirdas, Ušpuras, Eugenijus

Journal:

Nuclear Engineering and Design

Year:

2019

File:

PDF, 2.57 MB

2019

6

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

7

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

8

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

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

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

11

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

12

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

13

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

14

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

15

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

16

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

17

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

18

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

19

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

20

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

21

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

22

[ASME 18th International Conference on Nuclear Engineering - Xi’an, China (May 17–21, 2010)] 18th International Conference on Nuclear Engineering: Volume 2 - RBMK Fuel Rod Modelling and Investigation of Process During Operation Cycle

Kaliatka, Tadas, Marao, Aušra, Karalevičius, Renatas, Ušpuras, Eugenijus

Year:

2010

Language:

english

File:

PDF, 382 KB

english, 2010

23

Tritium and dust source term inventory evaluation issues in the European DEMO reactor concepts

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

Journal:

Fusion Engineering and Design

Year:

2019

Language:

english

File:

PDF, 445 KB

english, 2019

24

In memoriam of Eugenijus UÅ¡puras (1955â2019)

RimkeviÄius, Sigitas, Kaliatka, Algirdas, Urbonas, Rolandas

Journal:

Nuclear Engineering and Design

Year:

2020

File:

PDF, 160 KB

2020

25

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

26

Severe accident code-to-code comparison for two accident scenarios in a spent fuel pool

Coindreau, O., Jäckel, B., Rocchi, F., Alcaro, F., Angelova, D., Bandini, G., Barnak, M., Behler, M., Da Cruz, D.F., Dagan, R., Drai, P., Ederli, S., Herranz, L.E., Hollands, T., Horvath, G., Kaliatka

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 2.00 MB

english, 2018

27

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

28

Deterministic Analysis of Natural Circulation Events at the Ignalina NPP

Kaliatka, Algirdas, Uspuras, Eugenijus, Vileiniskis, Virginijus

Journal:

Science and Technology of Nuclear Installations

Year:

2008

Language:

english

File:

PDF, 2.15 MB

english, 2008

29

Best estimate approach for the evaluation of critical heat flux phenomenon in the boiling water reactors

Kaliatka, T., Kaliatka, A., Uspuras, E., Vaisnoras, M., Mochizuki, H., van Rooijen, W. F. G.

Journal:

Year:

2017

Language:

english

File:

PDF, 523 KB

english, 2017

30

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

31

[ASME 2017 25th International Conference on Nuclear Engineering - Shanghai, China (Sunday 2 July 2017)] Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management - Modeling of QUENCH 10 Experiment on Air Ingress Using RELAP/SCDAPSIM Mod 3.5

Kaliatka, Tadas, Uspuras, Eugenijus, Allison, Chris M.

Year:

2017

Language:

english

File:

PDF, 1.16 MB

english, 2017

32

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

33

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

34

Methodology of the source term estimation for DEMO reactor

Mazzini, Guido, Kaliatka, Tadas, Porfiri, Maria Teresa, Poggi, Luigi Antonio, Malizia, Andrea, Gaudio, Pasqualino

Journal:

Fusion Engineering and Design

Year:

2017

Language:

english

File:

PDF, 405 KB

english, 2017

35

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

36

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

37

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

38

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

39

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

40

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

41

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

42

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

43

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

44

[ASME 10th International Conference on Nuclear Engineering - Arlington, Virginia, USA (April 14–18, 2002)] 10th International Conference on Nuclear Engineering, Volume 4 - Uncertainty Analysis of RBMK-Related Experimental Data

Urbonas, Rolandas, Kaliatka, Algirdas, Liaukonis, Mindaugas

Year:

2002

Language:

english

File:

PDF, 354 KB

english, 2002

45

Analysis of Ingress of Coolant Accident to the Vacuum Vessel of the W7-X Fusion Experimental Facility

Kaliatka, Tadas, Uspuras, Eugenijus, Kaliatka, Algirdas

Journal:

Fusion Science & Technology

Year:

2017

Language:

english

File:

PDF, 1.21 MB

english, 2017

46

Integrated assessment of thermal hydraulic processes in W7-X fusion experimental facility

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

Journal:

Nuclear Engineering and Design

Year:

2017

Language:

english

File:

PDF, 2.06 MB

english, 2017

47

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

48

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

49

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

50

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

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