Results 11 to 20 of about 4,532 (263)
Neutronics calculation of the conceptual TRISO duplex fuel rod design
The duplex fuel pellet includes UO2 components as seed and ThO2 blanket, originally designed to increase the breeding rate of fissile materials in light water breeder reactors. However, the seed portion alone concentrates most of the energy released from
Mohamad Hairie Rabir +2 more
doaj +1 more source
Assessment of TMSR-500 Shutdown Capability
The molten salt reactor (MSR) is a generation IV reactor with liquid fuel having nearly zero excess reactivity. Due to the very low excess reactivity, it requires a small number of control rods worth to shut down the reactor.
A. Khakim +3 more
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Non-destructive evaluation of nuclear fuel rods using neutron radiography at the Tehran Research Reactor [PDF]
Three fresh fuel rods containing pellets inside zirconium tubes with three different enrichments and different dimensions have been evaluated using neutron radiography examinations at the Tehran Research Reactor. To obtain the information of the internal
M Choopan Dastjerdi +4 more
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Reliability analysis of helium pressure non-destructive testing method of the fuel rod
BackgroundCurrently, the destructive puncture manometry method is used to measure helium pressure inside fuel rods. However, this method is expensive and does not guarantee 100% coverage.
HUANG Fan +4 more
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A comparative study on the impact of Gd2O3 burnable neutron absorber in UO2 and (U, Th)O2 fuels
The performance of gadolinium burnable absorber (GdBA) for reactivity control in UO2 and (U, Th)O2 fuels and its impact on spent fuel characteristics was performed.
Edwin Humphrey Uguru +4 more
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The COLIBRI experimental program in the CROCUS reactor: characterization of the fuel rods oscillator [PDF]
The present article presents the mechanical characterization of the fuel rods oscillator developed for the purposes of the COLIBRI experimental program in CROCUS. COLIBRI aims at investigating the radiation noise related to fuel vibrations.
Lamirand Vincent +9 more
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QUALIFICATION OF ANC9 GENERIC INSERT METHODOLOGY (GIM) [PDF]
Discrete burnable poisons like the Wet Annular Burnable Absorber and Pyrex have been used in PWR core to improve core power distribution and provide more negative moderator temperature coefficient.
Zhang Baocheng +4 more
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In this study, road transportation tests were conducted with surrogate fuel assemblies under normal conditions of transport to evaluate the vibration and shock load characteristics of spent nuclear fuel (SNF). The overall test data analysis was conducted
JaeHoon Lim, Woo-seok Choi
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The paper considers various concentrations of burnable absorber (BA) Gadolinium (Gd) in the system of compensation of excess reactivity in the reactor of WWER type at the extended campaigns.
S. K. Rahman Anisur, M. A. Uvakin
doaj +1 more source
HTGR fuel rod deconsolidation [PDF]
High-Temperature Gas-Cooled Reactor fuel particles are bonded into rods by a carbonaceous matrix. In conjunction with the development of a system to determine fuel failure fractions from gamma analysis of individual particles, a technique was developed to separate the particles from the matrix after irradiation.
Tiegs, T. N., Ryan, E. L., Kania, M. J.
openaire +2 more sources

