Results 21 to 30 of about 186 (119)

Analyses of the OSU‐MASLWR Experimental Test Facility

Science and Technology of Nuclear Installations, Volume 2012, Issue 1, 2012., 2012
Today, considering the sustainability of the nuclear technology in the energy mix policy of developing and developed countries, the international community starts the development of new advanced reactor designs. In this framework, Oregon State University (OSU) has constructed, a system level test facility to examine natural circulation phenomena of ...
F. Mascari, G. Vella, B. G. Woods, F. D′Auria, Alessandro Del Nevo   +4 more
wiley   +1 more source

Review of Available Data for Validation of Nuresim Two‐Phase CFD Software Applied to CHF Investigations

Science and Technology of Nuclear Installations, Volume 2009, Issue 1, 2009., 2009
The NURESIM Project of the 6th European Framework Program initiated the development of a new‐generation common European Standard Software Platform for nuclear reactor simulation. The thermal‐hydraulic subproject aims at improving the understanding and the predictive capabilities of the simulation tools for key two‐phase flow thermal‐hydraulic processes
D. Bestion, H. Anglart, D. Caraghiaur, P. Péturaud, B. Smith, M. Andreani, B. Niceno, E. Krepper, D. Lucas, F. Moretti, M. C. Galassi, J. Macek, L. Vyskocil, B. Koncar, G. Hazi, Iztok Tiselj   +15 more
wiley   +1 more source

Estimation of local linear heat rate jump values in the variable loading mode [PDF]

Ядерна фізика та енергетика, 2011
A method of the WWER-1000 fuel element cladding durability analysis using the energy creep theory makes it possible to determinate the WWER-1000 reactor permissible operation time for the mode of varying loading. But the WWER-1000 axial segments and fuel
S. N. Pelykh, R. L. Gontar, T. V. Tsiselskaya   +2 more
doaj  

Comparative Study of Spectral Regulation Range of Excess Reactivity Control in Pressurized Water Reactors Using Zirconium Displacers for Uranium and Thorium Fuel Cycles

Глобальная ядерная безопасность, 2022
The compensation for the excess reactivity in the pressurized water reactors WWER is realized with high neutron absorber materials. The traditional excess reactivity regulation methods lead to unfeasible neutron utilization and reduce the breeding ...
A. I. Elazaka, V. I. Savander, G. V. Tikhomirov   +2 more
doaj   +1 more source

Reply to V. I. Borysenko's comment on the article: "Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000" [PDF]

Ядерна фізика та енергетика, 2020
: Reply to V. I. Borysenko's comment on the article: V. I. Skalozubov, I. L. Kozlov, Yu. A. Komarov, O. A. Chulkin, O. I. Piontkovskyi, "Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000" https://doi.org/10.15407 ...
V. I. Skalozubov, I. L. Kozlov, Yu. A. Komarov, V. Yu. Gryb, V. M. Vashchenko   +4 more
doaj   +1 more source

Mathematical Models for Investigation of WWER-1000/320 Transients

Nuclear and Radiation Safety, 2018
The paper presents mathematical models of the reactor WWER-1000/320, which are designed to investigate non-stationary operating modes of the reactor. The models in relative state variables include a point model of neutron kinetics with six groups of delayed neutrons and models of thermal processes, gradual heat generation, change in xenon concentration.
D. Lukinova, V. Severin, E. Nikulina
openaire   +2 more sources

Thermal Hydraulic Analysis of a Passive Residual Heat Removal System for an Integral Pressurized Water Reactor

Science and Technology of Nuclear Installations, Volume 2009, Issue 1, 2009., 2009
A theoretical investigation on the thermal hydraulic characteristics of a new type of passive residual heat removal system (PRHRS), which is connected to the reactor coolant system via the secondary side of the steam generator, for an integral pressurized water reactor is presented in this paper.
Junli Gou, Suizheng Qiu, Guanghui Su, Douna Jia, Xu Cheng   +4 more
wiley   +1 more source

Role of Passive Safety Systems in Chinese Nuclear Power Development

Science and Technology of Nuclear Installations, Volume 2009, Issue 1, 2009., 2009
Passive safety systems have been widely applied to advanced water‐cooled reactors, to enhance the safety of nuclear power plants. The ambitious program of the nuclear power development in China requires reactor concepts with high safety level. For the near‐term and medium‐term, the Chinese government decided for advanced pressurized water reactors with
X. Cheng, Y. H. Yang, Y. Ouyang, H. X. Miao, Dino A. Araneo   +4 more
wiley   +1 more source

The Use of Th in HTR: State of the Art and Implementation in Th/Pu Fuel Cycles

Science and Technology of Nuclear Installations, Volume 2009, Issue 1, 2009., 2009
Nowadays nuclear is the only greenhouse‐free source that can appreciably respond to the increasing worldwide energy demand. The use of Thorium in the nuclear energy production may offer some advantages to accomplish this task. Extensive R&D on the thorium fuel cycle has been conducted in many countries around the world.
Guido Mazzini, Eleonora Bomboni, Nicola Cerullo, Emil Fridman, Guglielmo Lomonaco, Eugene Shwageraus, Jim Kuijper   +6 more
wiley   +1 more source

Use of the Natural Circulation Flow Map for Natural Circulation Systems Evaluation

Science and Technology of Nuclear Installations, Volume 2008, Issue 1, 2008., 2008
The aim of this paper is to collect and resume the work done to build and develop, at the University of Pisa, an engineering tool related to the natural circulation. After a brief description of the different loop flow regimes in single phase and two phase, the derivation of a suitable tool to judge the NC performance in a generic system is presented ...
M. Cherubini, W. Giannotti, D. Araneo, F. D′Auria, Dilip Saha   +4 more
wiley   +1 more source