Results 291 to 300 of about 2,271,236 (350)

Thermal-Hydraulic Experimental Testing of the MYRRHA Wire-Wrapped Fuel Assembly

Nuclear Technology, 2019
In recent years, extensive thermal-hydraulic experimental tests have been performed on the lead-bismuth eutectic (LBE)–cooled, wire-wrapped fuel assembly (FA) of MYRRHA.
G. Kennedy, K. Van Tichelen, J. Pacio, I. Di Piazza, H. Uitslag-Doolaard   +4 more
semanticscholar   +1 more source

Thermal-hydraulics analysis of flow blockage events for fuel assembly in a sodium-cooled fast reactor

International Journal of Heat and Mass Transfer, 2019
The subchannel code ATHAS-LMR has been improved for analyzing thermal-hydraulics characteristics of flow blockage events in the fuel assembly of a sodium-cooled fast reactor (SFR).
Peng Du, J. Shan, Bo Zhang, L. Leung
semanticscholar   +1 more source

Fuel assembly burnup calculations for VVER fuel assemblies with the MONTE CARLO code SERPENT

Kerntechnik, 2014
Abstract The Monte Carlo code SERPENT (http://montecarlo.vtt.fi) is tested and validated for different fuel configurations but not for VVER fuel assemblies with Gd fuel pins and enrichment profiling. The presentation outlines the results obtained during fuel assembly burnup calculations for VVER-440 and VVER-1000 reactor types with Gd ...
openaire   +1 more source

Fuel Pellet, Element and Assembly

2023
Fuels that are fabricated for water-cooled power reactors are based on ceramic uranium dioxide (UO2), sintered from the powder to form fuel pellets. Fuel pellets, usually about 10 mm to 12 mm in diameter and 10 to 15 mm in length, are stacked in zirconium alloy (i.e., zircaloy) tubes, forming fuel elements.
openaire   +1 more source

Fuel Pin and Assembly Design

2011
This chapter deals with the mechanical designs of fuel pins and assemblies. These core components must be designed to withstand the high temperature, high flux environment of a fast spectrum reactor for a long irradiation exposure time. In this chapter we will describe many of the factors that influence this design, and we will examine in some detail ...
Alan Waltar, Donald Todd
openaire   +1 more source

Seismic analysis of PWR-RCC fuel assemblies

Nuclear Engineering and Design, 1982
Abstract The present paper investigates the dynamic behaviour of PWR-RCC fuel assemblies under seismic excitation. A simple vibrational model of the fuel assembly is proposed, which leads to natural frequencies whose spacing agree with experimental data. Available experimental results are reviewed.
Preumont, André, Thomson, P., Parent, José   +2 more
openaire   +2 more sources

Comparison of BWR fuel assembly options for minor actinide recycling

Annals of Nuclear Energy, 2019
Nuclear energy production generates Minor Actinide (MA) and Plutonium (Pu) isotopes, being these ones the main reason for the longtime storage of the depleted fuel assemblies.
E. Martínez, G. Alonso, R. Ramírez, Rogelio Castillo   +3 more
semanticscholar   +1 more source

PWR Fuel Assembly Modal Testing and Analysis

Flow-Induced Vibration, 2003
Pressurized Water Reactor (PWR) seismic or Lost Of Coolant Accident (LOCA) loads could result in impacts between nuclear fuel assemblies or between fuel assemblies and the core baffles. Forces generated during these shocks are often the basis for the determination of the maximum loads and of the spacer grid and fuel rod design.
Collard, B., Pisapia, Stéphane, Bellizzi, Sergio, Witters, F.   +3 more
openaire   +2 more sources

Self-Assembly in Fuel Cells

2017
© 2017 Elsevier Ltd. All rights reserved. Proton exchange membrane fuel cell (PEMFC) is an electrochemical energy conversion technology to directly convert the chemical energy of fuels to electricity with high efficiency and low greenhouse gas emission.
Zhang, J., Jiang, San Ping
openaire   +2 more sources

Fuel Cycle Economy of Accident Tolerant Fuel Assemblies

Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, 2018
Taking the large commercial pressurized water reactor and its mature fuel assembly as reference, this paper has analyzed economic performance of two accident tolerant fuel (ATF) designs based on once-through fuel cycle. The results show that the fuel cycle costs of both AT F designs have grown due to application of BeO powder, which is expensive.
Xu Duoting, Liu Tong, Huang Heng
openaire   +1 more source