Results 21 to 30 of about 3,448 (263)
Thermalhydraulics of advanced 37-element fuel bundle in crept pressure tubes
A CANDU-6 reactor, which has 380 fuel channels of a pressure tube type, is suffering from aging or creep of the pressure tubes. Most of the aging effects for the CANDU primary heat transport system were originated from the horizontal crept pressure tubes.
Park Joo Hwan, Song Yong Mann
doaj +1 more source
The present work discusses two different models of boiling water reactor (BWR) bundle to compare the neutronic characteristics of uranium dioxide (UO2) and uranium zirconium hydride (UZrH1.6) fuel. Each bundle consists of four assemblies.
Ahmed Abdelghafar Galahom
doaj +1 more source
Thermal-mechanical characteristics of helical cruciform fuel bundle
BackgroundAs an innovative nuclear fuel assembly, the helical cruciform fuel (HCF) assembly has the characteristics of large specific heat transfer area, short heat conduction path, strong inter-channel mixing and free from the grid spacers.
CONG Tenglong +4 more
doaj +1 more source
Monte Carlo Few-Group Constant Generation for CANDU 6 Core Analysis
The current neutronics design methodology of CANDU-PHWRs based on the two-step calculations requires determining not only homogenized two-group constants for ordinary fuel bundle lattice cells by the WIMS-AECL lattice cell code but also incremental two ...
Seung Yeol Yoo +2 more
doaj +1 more source
In terms of safety and the efficient management of spent fuel storage, detecting failed fuel is one of the most important tasks in a CANada Deuterium Uranium (CANDU) reactor operation.
JONG-YOUL PARK +2 more
doaj +1 more source
Geometric configuration of fuel assembly for small lightweight lead-bismuth reactor
BackgroundThe neutronics and thermal-hydraulic characteristics of lead-bismuth cooled reactors are significantly affected by the geometric configuration of fuel assembly and lattice parameters.
WANG Chang +5 more
doaj +1 more source
Power flattening in the fuel bundle of a CANDU reactor
Abstract The strong non-uniformity of the fission power production density in the CANDU fuel bundle could have been mitigated to a great degree. A satisfactory power flattening has been achieved through an appropriately evaluated method by varying the composition of the LWR spent fuel/ThO2 mixture in a CANDU fuel bundle in radial direction and ...
Şahin, Sümer +2 more
openaire +4 more sources
CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FOR THE DECOMMISSIONING OF THE HORIZONTAL FUEL CHANNELS IN THE CANDU 6 NUCLEAR REACTOR PART 5 - FUEL CHANEL DECOMMISSIONING [PDF]
As many nuclear power plants are reaching their end of lifecycle, the decommissioning of these installations has become one of the 21st century’s great challenges. Each project may be managed differently, depending on the country, development policies,
Gabi ROSCA FARTAT +2 more
doaj
Realistic thermal analysis of the CANDU spent fuel dry storage canister
Thermal analysis of the CANDU spent fuel dry storage canister is very important to ensure the integrity of the spent fuel. The analyses have been conducted using a conservative approach, with a particular focus on the peak cladding temperature (PCT) of ...
Tae Gang Lee +4 more
doaj +1 more source
Gut microbiome and aging—A dynamic interplay of microbes, metabolites, and the immune system
Age‐dependent shifts in microbial communities engender shifts in microbial metabolite profiles. These in turn drive shifts in barrier surface permeability of the gut and brain and induce immune activation. When paired with preexisting age‐related chronic inflammation this increases the risk of neuroinflammation and neurodegenerative diseases.
Aaron Mehl, Eran Blacher
wiley +1 more source

