Zobrazeno 1 - 10
of 56
pro vyhledávání: '"R. Gencheva"'
Autor:
R. Gencheva, M. Petrova, P. Kraleva, S. Hadjidekova, M. Radanova, N. Conev, D. Stoyanov, J. Arabadjiev, E. Tazimova, S. Bachurska, M. Eneva, M. Tsvetkova, G. Zhbantov, T. Karanikolova, D. Manov, A. Ivanova, M. Taushanova‐Hadjieva, R. Staneva, E. Dimitrova, I. Donev
Publikováno v:
Cancer Reports, Vol 7, Iss 2, Pp n/a-n/a (2024)
Abstract Background and aims In approximately 40% of patients with HER2‐negative/HR‐positive breast cancer tumors, the PIK3CA gene is mutated. Despite this, clinical outcomes vary between studies in this cohort. We aimed to ascertain the prevalen
Externí odkaz:
https://doaj.org/article/560a52d4d20f4541b143be1d8674397e
Autor:
A. Alexeyenko, O.T. Brustugun, I.J. Zwicky Eide, R. Gencheva, Z. Kosibaty, Y. Lai, L. de Petris, G. Tsakonas, O. Grundberg, B. Franzen, K. Viktorsson, R. Lewensohn, P. Hydbring, S. Ekman
Publikováno v:
Journal of Thoracic Oncology. 17:S156
Publikováno v:
Nuclear Engineering and Design. 351:80-86
This paper presents an assessment and comparison of the core degradation progression in four Station Blackout (SBO) scenarios analysed by the ASTEC computer code. Two types of SBO scenarios namely with high- and low-pressure conditions are considered
Assessing the Impact of Passive Autocatalytic Recombiners on the Accident Progression in a VVER 1000
Publikováno v:
Proceedings of the 30th European Safety and Reliability Conference and 15th Probabilistic Safety Assessment and Management Conference.
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Publikováno v:
Annals of Nuclear Energy. 159:108315
The presented paper discuses a study of core degradation behavior where a Medium Break Loss of Coolant Accident (MB LOCA) with a150 mm internal diameter along with station blackout (SBO) was the initiating event. One of the goals of this work was the
Publikováno v:
Proceedings of the 29th European Safety and Reliability Conference (ESREL).
Publikováno v:
Nuclear Engineering and Design
This study aims to assess the applicability of the in-vessel melt retention (IVMR) strategy with external vessel water cooling to the reactors of VVER-1000/v320 type. IVMR strategy is one of the feasible solutions to mitigate reactor vessel failure a
Publikováno v:
Nuclear Engineering and Design. 295:441-456
During the development of symptom-based emergency operating procedures (SB-EOPs) for VVER440/v230 units at Kozloduy Nuclear Power Plant (NPP) a number of analyses have been performed using the RELAP5/MOD3 ( Carlson et al., 1990 ). Some of them invest
Publikováno v:
Annals of Nuclear Energy
This investigation was done to assess the applicability of the In-Vessel Melt Retention (IVMR) strategy with external vessel water cooling for the reactors of VVER-1000/320 type. The IVMR strategy has been studied in different countries and the exist