Results 41 to 50 of about 705,564 (243)
Usually the synthesis of two-dimensional and one-dimensional discrete ordinate calculations is used to evaluate neutron fluence on VVER-1000 reactor pressure vessel (RPV) for prognosis of radiation embrittlement.
Dzhalandinov A. +8 more
doaj +1 more source
The broad-group library BGL1000_B7 for neutron and gamma transport calculations in VVER-1000 internals, RPV and shielding was carried out on a base of fine-group library v7-200n47g from SCALE-6 system.
Voloschenko Andrey +3 more
doaj +1 more source
The Institute of Neutron Physics and Reactor Technology (INR) is involved in the qualification of coupled codes for reactor safety evaluations, aiming to improve their prediction capability and acceptability.
V. Sánchez +3 more
doaj +1 more source
Post-irradiation annealing of neutron-irradiated reactor pressure vessel steels is a matter of both technical and scientific interest. Small-angle neutron scattering (SANS), while being sensitive to nm-sized irradiation-induced solute-atom clusters ...
A. Ulbricht +4 more
semanticscholar +1 more source
Assessment of the possibility for large-scale 238Pu production in a VVER-1000 power reactor
The paper presents the estimates for the possibility for large-scale production of 238Pu in the core of a VVER-1000 power reactor. The Np-fraction of minor actinides extracted from transuranic radioactive waste is proposed to be used as the starting ...
A. Shmelev +5 more
semanticscholar +1 more source
Brittle fracture resistance of reactor pressure vessel steels in the initial state [PDF]
The authors investigate the influence of chemical and structural inhomogeneity on the brittle fracture resistance (BFR) of VVER vessel materials in the initial state (without irradiation).
Nikolay P. Anosov +5 more
doaj +3 more sources
Development of nodal diffusion code RAST-V for Vodo–Vodyanoi Energetichesky reactor analysis
This paper presents the development of a nodal diffusion code, RAST-V, and its verification and validation for VVER (vodo–vodyanoi energetichesky reactor) analysis.
Jaerim Jang +2 more
doaj +1 more source
Про создание конечно-элементной модели корпуса главного циркуляционного насоса блока АЭС типа ВВЭР-1000 [PDF]
Розглянуто проблеми створення скінченно-елементної моделі корпуса головного циркуляційного насоса блоку АЕС типу ВВЕР-1000, виявлені причини їхньої появи, запропоновані підходи, що дозволяють успішно їх перебороти.
Рудаков, К. Н.
core +1 more source
The paper presents the results of studies into the interassembly coolant interaction in the Temelin nuclear power plant (NPP) VVER-1000 reactor core.
S.M. Dmitriev +5 more
doaj +1 more source
This paper presents the results obtained from numerical evaluations for the possibility of large-scale 238Pu production in the light-water VVER-1000 reactor and the reactivity effect caused by the loss-of-coolant accident in the central fuel assembly of ...
A. Shmelev +5 more
semanticscholar +1 more source

