Results 151 to 160 of about 9,551,406 (202)
Investigating Hydrogen in Zirconium Alloys by Means of Neutron Imaging. [PDF]
Materials (Basel)Weick S, Grosse M.
europepmc +1 more source
Developments, challenges and prospects in thermal-hydraulic research on accident tolerant fuel. [PDF]
HeliyonLi Y +5 more
europepmc +1 more source
Approaching Dynamic PSA Within CANDU 6 NPPs
18th International Conference on Nuclear Engineering: Volume 3, 2010 The plant dynamics and the interactions of plant systems and operator with the random evolution of parameters led to the development of dynamic reliability methodologies. The present paper approaches a dynamic PSA methodology by making use of the thermal–hydraulic model of CANDU 6 reactor, implemented in RELAP5 Mod.3.3, and of IDDA code.
M. Lontos, M. Mazzini, D. Mazzini
openaire +2 more sources
Some of the next articles are maybe not open access.
Related searches:
Related searches:
Comparative assessment of CANDU 6 and Sodium-cooled Fast Reactors for nuclear desalination
Desalination, 2016Abstract A comparative assessment is reported of two systems for nuclear desalination. The systems use Reverse Osmosis (RO) for desalination and are coupled with either a CANDU 6 nuclear reactor or a Sodium-cooled Fast Reactor (SFR). Exergy analysis is used to assess the performance of the electric power generation and desalination processes, and ...
Marc A. Rosen +2 more
exaly +2 more sources
The core pressure drop characteristics in a CANDU 6 reactor
Annals of Nuclear Energy, 2013Abstract The core pressure drop characteristics in a CANDU 6 have been examined to reveal the mechanism inducing the difference in the core pressure drop among four passages. The general characteristics for the inlet header temperature and core pressure drop are deduced from the measured data of CANDU 6 NPPs.
Jun Ho Bae, Jong Yeob Jung
openaire +1 more source
Applications of ASTEC integral code on a generic CANDU 6
Nuclear Engineering and Design, 2015Abstract In case of a hypothetical severe accident in a nuclear power plant, the corium consisting of the molten reactor core and internal structures may flow onto the concrete floor of containment building. This would cause an interaction between the molten corium and the concrete (MCCI), in which the heat transfer from the hot melt to the concrete ...
Gabriela Radu, Ilie Prisecaru
openaire +1 more source
BEPU Approach in the CANDU 6 Severe Accident Analysis
2019 International Conference on ENERGY and ENVIRONMENT (CIEM), 2019The worst nuclear accident after Cernobil (in April 1986), the Fukushima Daichii accident from March 11th, 2011 has increased nuclear experts interest, all over the world, on the implementation of severe accident management measures in order to maintain the integrity of the safety barriers.
Robert Musoiu +3 more
openaire +1 more source