A 3D stylized half-core CANDU benchmark problem

Pounders, Justin M.; Rahnema, Farzad; Serghiuta, Dumitru; Tholammakkil, John

doi:10.1016/j.anucene.2010.10.018

Cited by 22 publications

(6 citation statements)

References 2 publications

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“…A heavy water reflector completely surrounds the fuel lattice in the exterior radial direction. The reflector extends to at least two lattice pitches radially beyond the outer-most fuel channels [8].…”

Section: David Publishingmentioning

confidence: 99%

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Analysis of CANDU Reactor Performance Using Thorium Fuel: Comparison with Natural UO2 Case

Ellithi¹,

AL-Khawlani²

2020

JMSE-B

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The purpose of the paper is to study the performance of the CANDU (Canada Deuterium Uranium) reactor when the reactor core is loaded with thorium fuel mixed with plutonium isotopes with ratio 3 and 5%. A three dimensional model is designed for the core of CANDU reactor. The computer code MCNPX (Monte Carlo N-Particle Transport) is used to calculate the processes in its core. The results are compared with natural UO 2 case which is the typical fuel of the reactor. The results show that the multiplication factor of the reactor is higher even in the case of thorium fuel mixed with 3% plutonium isotopes, which indicates longer neutron life cycle length and more economic utilization of the reactor.

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Section: David Publishingmentioning

confidence: 99%

“…Each rod consists of a solid stainless steel cylinder (shim) that is centered in a stainless steel tube. The shim and tube are composed of two vertical segments with slightly different diameters [8,9].…”

Section: David Publishingmentioning

confidence: 99%

Analysis of CANDU Reactor Performance Using Thorium Fuel: Comparison with Natural UO2 Case

Ellithi¹,

AL-Khawlani²

2020

JMSE-B

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“…This work simulates the full-core reactor and considers the dimensions, geometric characteristics and composition of main structural components from previous studies [13][14][15][16]. Two models were simulated to evaluate the neutronic behavior due to different coolant types.…”

Section: Configuration Of Candu-6 Corementioning

confidence: 99%

“…The goal is to study the neutronic behavior of core with different number of RFC (Reprocessed Fuel Channels) in the two configurations and compare them to the reference core loaded with FNU (Fresh Natural Uranium). This core was based on preceding works [13,14], which evaluates a hypothetical extreme condition considering all CANDU fuel channels with a fresh fuel bundle. Therefore, the FNU comprises a fuel bundle at zero burnup.…”

Section: Introductionmentioning

confidence: 99%

Neutronic evaluation of CANDU-6 core using reprocessed fuels

et al. 2020

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The spent fuel from a PWR still contains some amount of fissile materials depending on their initial enrichment and the burnup. Thus, spent fuel from PWRs containing about 1.5% of fissile material could be used as fuel for CANDU reactors after some fission products are removed from it. Thus, an important proposal is the DUPIC cycle, where spent fuels from a PWR are packaged into a CANDU fuel bundle using mechanical reprocessing but without the need of chemical reprocessing. When it is refueled with reprocessed fuel, the reactivity of the system increases, and this behavior may affect the safety parameters of the reactor. Therefore, this work studies the neutronic parameters of two reprocessing fuel techniques: AIROX and OREOX, which are evaluated for two different cores configuration. The first one considers heavy water as a moderator and coolant. The second one considers heavy water and light water as moderator and coolant respectively. These studies evaluate the core behavior based on the different number of reprocessed fuels channels and compare them with the reference core. To perform the simulation the MCNPX was used to calculate the effective multiplication factor, fuel temperature coefficient of reactivity, void reactivity coefficient, and neutron flux, which were evaluated at steady state condition for the different cases. The results show that the presence of parasitic absorbers in the reprocessed fuels hardens the neutron spectrum. This behavior provokes an increase in the core reactivity, in the fuel temperature coefficient and in the void reactivity coefficient. Among these parameters, the use of light water reduces the core reactivity but do not improve the fuel temperature coefficient and the void reactivity coefficient.

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“…Zone controller units regulates the reactor power of each zone by varying the amount of light water in the corresponding compartment. Incremental cross sections are thus considered for zone controller units and adjuster rods [2,[6][7][8].…”

Section: Introductionmentioning

confidence: 99%

Analysis of Neutronic Parameters for Supercell of CANDU Reactor Using MCNPX Code

EL-Khawlani¹,

Ibrahim²,

Ellithi³

2013

JMSE-B

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MCNPX code has been used for modeling and simulation of a supercell of CANDU Fuel, the supercell consists of two fuel bundle and adjuster rod. The fuel bundle are burnt in normal operation conditions of CANDU reactors. Natural uranium fuel is used in the model. The multiplication factor of the bundle is calculated during fuel burnup. The concentration of both uranium and plutonium isotopes are analysed in the bundle. The worth of the adjuster rod is calculated. Comparison of multiplication factor and worth of the adjuster rod with the previous published references showed good agreement.

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A 3D stylized half-core CANDU benchmark problem

Cited by 22 publications

References 2 publications

Analysis of CANDU Reactor Performance Using Thorium Fuel: Comparison with Natural UO2 Case

Analysis of CANDU Reactor Performance Using Thorium Fuel: Comparison with Natural UO2 Case

Neutronic evaluation of CANDU-6 core using reprocessed fuels

Analysis of Neutronic Parameters for Supercell of CANDU Reactor Using MCNPX Code

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