Results 31 to 40 of about 9,237 (168)

Effect of KLT-40S Fuel Assembly Design on Burnup Characteristics

open access: yesEnergies, 2023
The KLT-40S is a small modular reactor developed by Russia based on the KLT-40 reactor with two fuel assembly designs: a four-ring and a five-ring. Few studies have been published on fuel assembly and power-flattening designs for the KLT-40S.
Zedong Zhou   +5 more
doaj   +1 more source

Piloted Ignition of Cylindrical Wildland Fuels Under Irradiation

open access: yesFrontiers in Mechanical Engineering, 2019
Recent mega wildfires have become one of the most dangerous and devastating hazards, with a wide range of negative impacts on the economy, society, and environment.
Shaorun Lin   +6 more
doaj   +1 more source

The effect of axial fuel rod power profile on fuel temperature and cladding strain [PDF]

open access: yesNuclear Technology and Radiation Protection, 2010
The most limiting design criteria for nuclear reactor normal operating conditions (ANS Condition I) are known to be rod internal pressure and cladding oxidation, while those for nuclear reactor transient operating conditions (ANS Conditon II) to be ...
Kim Kyu-Tae
doaj   +1 more source

Numerical simulation of the molten fuel relocation in fuel rod

open access: yesJournal of Physics: Conference Series, 2019
Abstract Thermal destruction of fuel rods is one of the most hazardous accidents in nuclear power plants. Fuel melt contains a lot of fission products that can release and start to transport along reactor loops. Relocation of the fuel melt can change the power of reactor due to feedback between density of materials and neutron field in ...
E V Usov   +4 more
openaire   +1 more source

Analytical investigation of the fuel rod destruction and melt relocation along the surface of the fuel rod

open access: yesJournal of Physics: Conference Series, 2019
Abstract To simulate fuel rod thermal destruction, analytical approaches were developed. Approaches are based on solving the Stefan problem and solving the equation of motion of the molten materials. The paper contains a brief description of the ways to obtain analytical solutions and applicability limits of the solutions. Calculation of
openaire   +1 more source

The ‘Fuel Rod Analysis ToolBox’: A general program for preparing the input of a fuel rod performance code

open access: yesAnnals of Nuclear Energy, 2015
AbstractThis paper gives an overview of the new ‘Fuel Rod Analysis Toolbox’, which is a program for the pre-processing of input data for fuel rod performance codes with a graphical user interface. It consists of three different modules that can handle several tasks such as data condensation, merging and synchronization.
Lassmann, K.   +3 more
openaire   +1 more source

Key results from examinations of seven high burnup pressurized water reactor spent nuclear fuel rods

open access: yesFrontiers in Nuclear Engineering
At present, spent nuclear fuel (SNF) assemblies discharged from US commercial power plants are placed into dry storage following a short cooling time (<10 years) in the plant’s spent fuel pool.
Rose Montgomery   +3 more
doaj   +1 more source

Fuel Assembly Design Symmetry Implications for a Boiling Water Reactor

open access: yesJournal of Nuclear Engineering
Fuel assembly design in Boiling Water Reactors has evolved to achieve more efficient use of uranium by optimizing the moderator distribution within the fuel assembly and increasing the number of smaller-diameter fuel rods to prevent rod power peaking ...
Hector Hernandez-Lopez, Gustavo Alonso
doaj   +1 more source

Flow and Heat Transfer Analysis in Lead-bismuth Reactor Core under Rod Bending Condition

open access: yesYuanzineng kexue jishu, 2023
Liquid metal-cooled fast reactors (LMFRs) are being investigated in many countries as the next-generation nuclear reactors. Fuel rods in LMFRs are commonly arranged in a triangular pitch and assembled in a hexagonal fuel wrapper.
QIU Hanrui;LI Jun;WANG Mingjun;ZHANG Jing;TIAN Wenxi;SU Guanghui
doaj  

Impact of revised RG 1.183 on source terms and radiological consequences of rod ejection accident for the HRP1000 reactor

open access: yesInternational Journal of Advanced Nuclear Reactor Design and Technology
This paper compares and analyzes the impact of the revised RG 1.183 on the source term and radioactive consequences of the rod ejection accident. The revision of RG 1.183 has resulted in changes to key assumptions in the source term analysis of the rod ...
Yichen Chen   +4 more
doaj   +1 more source

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