Results 71 to 80 of about 302 (158)

VIPRE modeling of VVER-1000 reactor core for DNB analyses

, 1995
Based on the one-pass modeling approach, the hot channels and the VVER-1000 reactor core can be modeled in 30 channels for DNB analyses using the VIPRE-01/MOD02 (VIPRE) code (VIPRE is owned by Electric Power Research Institute, Palo Alto, California).
Y Sung, Q Nguyen, J Cizek
openaire   +2 more sources

Estimation of material degradation of VVER-1000 baffle

EPJ Web of Conferences, 2017
The planned lifetime of the first commercial VVER-1000 units were designed for 30 to 35 years. Most of the early VVER plants are now reaching and/or passing the 35-year mark.
Harutyunyan Davit, Košál Michal, Vandlík Stanislav, Hojná Anna, Schulc Martin, Flibor Stanislav   +5 more
doaj   +1 more source

Comparative Analysis of Emergency Planning Zone and Control Room Habitability for Potential Nuclear Reactor Deployment in Ghana. [PDF]

Int J Environ Res Public Health, 2022
Christina P, Kim J.
europepmc   +1 more source

Study of Fast Transient Pressure Drop in VVER-1000 Nuclear Reactor Using Acoustic Phenomenon

Science and Technology of Nuclear Installations, 2018
This article aims to simulate the sudden and fast pressure drop of VVER-1000 reactor core coolant, regarding acoustic phenomenon. It is used to acquire a more accurate method in order to simulate the various accidents of reactor core. Neutronic equations
Soroush Heidari Sangestani, Mohammad Rahgoshay, Naser Vosoughi, Mitra Athari Allaf   +3 more
doaj   +1 more source

CFD analysis of coolant mixing in VVER-1000/V320 reactor pressure vessel

Annals of Nuclear Energy
This study presents a code-to-code and model-to-model comparison of coolant mixing in the VVER-1000/V320 Kozloduy Unit 6 nuclear power plant using Computational Fluid Dynamics (CFD). Four different CFD codes were used to simulate coolant mixing in the reactor vessel, namely ANSYS Fluent, ANSYS CFX, TrioCFD, and STAR-CCM+.
Böttcher, M, Bernard, O, Mas, A, Sanchez, V, Nop, R, Belaunde, F, Bourcier, C, Ruban, D, Hashymov, A, Halim, Ossama, Pucciarelli, A, Forgione, N   +11 more
openaire   +5 more sources

Investigation of the influence of various factors on the power of heat exchange by radiation

Trudy Odesskogo Politehničeskogo Universiteta, 2017
The issue of lack of knowledge of radiation heat transfer process has been repeatedly raised in various studies. Despite the fact that works on study of heat transfer by radiation covers a wide range of different industries, it should be noted the lack ...
Олександр Вікторович Корольов, Олег Петрович Іщенко   +1 more
doaj   +2 more sources

Precise calculation of neutron-capture reactions contribution in energy release for different types of VVER-1000 fuel assemblies

EPJ Web of Conferences, 2017
Precise calculation of energy release in a nuclear reactor is necessary to obtain the correct spatial power distribution and predict characteristics of burned nuclear fuel.
Tikhomirov Georgy, Bahdanovich Rynat, Pham Phu   +2 more
doaj   +1 more source

Microstructure and Mechanical Properties of Ni-20Cr-Eu₂O₃ Composites Prepared by Vacuum Hot Pressing. [PDF]

Materials (Basel), 2023
Zhou Y, Yue H, Ma Z, Guo Z, Zhang J, Wang L, Yan G.   +6 more
europepmc   +1 more source

Research Progress of Steels for Nuclear Reactor Pressure Vessels. [PDF]

Materials (Basel), 2022
Zhou L, Dai J, Li Y, Dai X, Xie C, Li L, Chen L.   +6 more
europepmc   +1 more source

A review of the application of artificial intelligence to nuclear reactors: Where we are and what's next. [PDF]

Heliyon, 2023
Huang Q, Peng S, Deng J, Zeng H, Zhang Z, Liu Y, Yuan P.   +6 more
europepmc   +1 more source