| Project No. |
Publication Title |
Link |
| 833.2 METCOR |
Corrosion of vessel steel during its interaction with molten corium:Part 1: |
Nuclear Engineering and Design; Volume 236, Issue 17, September 2006, Pages 1810-1829 |
| 833.2 METCOR |
Corrosion of vessel steel during its interaction with molten corium: Part 2: Model development |
Nuclear Engineering and Design; Volume 236, Issue 13, July 2006, Pages 1362-1370 |
| 833.2; 1950.2 |
Corium phase equilibria based on MASCA, METCOR and CORPHAD results. |
Nuclear Engineering and Design; Volume 238, Issue 10, October 2008, Pages 27861-2771 |
| 833.2 METCOR |
VVER vessel steel corrosion at interaction with Molten corium in oxidizing atmosphere |
Nuclear Engineering and Design; Volume 239, Issue 6, June 2009, Pages 1103-1112 |
| 1648.2 QUENCH-VVER; 3194, 3690 PARAMETER |
High-temperature oxidation and quench behaviour of Zircaloy-4 and E110 cladding alloys |
Progress in Nuclear Energy, Volume 52, Issue 1, January 2010, Pages 19-36 |
| 1950.2 CORPHAD |
Phase diagram of the ZrO2-Fe system. |
Journal of Nuclear Materials; Volume 348, Issues 1-2, 1 January 2006, Pages 114-121 |
| 1950.2 CORPHAD |
Phase diagram of the UO2-FeO1+x system. |
Journal of Nuclear Materials; Volume362, Issue 1, 15 May 2007, Pages 46-52 |
| 1950.2 CORPHAD |
Eutectic crystallization in the FWEO.5-UO2+x-ZrO2 system. |
Journal of Nuclear Materials; Volume 389, Issue1, 15 May 2009, Pages 52-56 |
| 1950.2 CORPHAD |
Improvement of the European thermodynamic database NUCLEA. |
Progress in Nuclear Energy; Volume 52, Issue 1, January 2010, Pages 84-96 |
| 3345 EVAN |
Influence of corium ocidation on fission product release from molten pool. |
Nuclear Engineering and Design; Volume 240, Issue 5, May 2010, Pages 1229-1241 |
| 3194 PARAMETER |
Behacior of a model VVER fuel assembly under the conditions of an unanticipated accidenat with Cooldawn by pouring water from above. |
Atomic Energy (translated from Russian). Volume 104, Nurmber 5 / Mai 2008. pp. 360364 |
| 3813 PRECOS |
Phase equilibria in the FeO1+x-UO2-ZrO2 system in the FeO1+x-enriched domain. |
journal of Nuclear Materials, Volume 400, Issue 2, 15 May 2010, Pages 119-126. |
| 3818 PRECOS |
Eutectic crystallization in the FeO1.5-UO2+x-ZrO2 system. |
Journal of Nuclear Materials; Volume 389, Issue 1, 15 May 2009, Pages 52-56, Thermochemistry and Thermophysics of Nuclear Materials, Poceedings of the Twelfth Symposium on Thermochemistry and Thermophysics of Nuclear Materials. |
| all projects |
Servere accident research in the core degration area: An example of effective international cooperation between the European Union (EU) and the Commonwealth of Independent States (CIS) by the International Science and Technology Center |
Nuclear Engineering and Design 252 (2012) 226-241 |
