Investigating the Performance and safety features of Pressurized water reactors using the burnable poisons

Reda, Sonia M.; Mustafa, Sayed Saeed; Elkhawas, Nourhan A.

doi:10.1016/j.anucene.2020.107354

Cited by 16 publications

(1 citation statement)

References 12 publications

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“…During the reactor operation, fuel composition changes in terms of quantity of fissile, fertile and poisoning isotopes. Fissile isotopes as U-235 and Pu-239 are depleted continuously as fissions take place, while fertile isotopes as U-238 and Th-232 are transformed into Pu-239 and U-233 respectively 16 . The production of poisonous isotopes, such as Xe-135, quickly accumulates and reaches to an equilibrium state, which in turn helps in regulating the reactivity of the core.…”

Section: Resultsmentioning

confidence: 99%

The effect of control rods on the reactivity and flux distribution of BWR 4 bundle using MCNPX Code

Mustafa

2021

Sci Rep

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This paper has three main objectives related to the neutronic and burnup analysis of the BWR (Boiling Water Reactor) Four-Lattice. The first objective is to provide partial validation of the MCNPX code for this lattice by comparing its results with Scale-5.1 results. Validation of the MCNPX to calculate effective multiplication factor and reactivity rod worth for the F-Lattice is provided. This is carried out in case of instantly removing the control blade and replacing it with a graphite moderator. Moreover, spatial neutron flux distributions using F-mesh card over the bundle and the control blade are investigated at inserting and withdrawing the B4C. The second objective is to perform parametric design studies of the F-Lattice. Areas of particular interest are the effect of increased or decreased blade width on the neutron flux throughout the bundle. It is found that the presence of carbon in the control blade at withdrawing the B4C makes the reactor supercritical, (K-eff = 1.22206). On the other hand, the use of B4C blade presents (K-eff = 0.93521). Consequently, the reactivity of 10% B4C thinner case is higher that of 10% B4C thicker. The simulation also showed that the B4C blade had an effective role in decreasing the thermal flux at the periphery of the bundle. This is contrast to the effect of carbon that moderates fast to thermal neutrons. The third part of this work aims at studying the burnup calculations using MCNPX code for 30 days burn with 1 day time step then for 20 months burn with 2 week time steps for the lattice. At the end of the work, it is very important to determine the most proper bundle model that achieves a prolonged fuel burn and flatting thermal flux distribution. For reaching this goal, three cases (B4C, 10% thinner of B4C and 10% thicker) are simulated by MCNPX code till 70 GWd/ton. It is found that the B4C and 10% thicker are the appropriate models that can satisfy the safety considerations of the Compact Modular Boiling Water Reactor.

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Section: Resultsmentioning

confidence: 99%

The effect of control rods on the reactivity and flux distribution of BWR 4 bundle using MCNPX Code

Mustafa

2021

Sci Rep

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Investigating core axial power distribution with multi-concentration gadolinium in PWR

Peng

Wang

et al. 2022

NUCL SCI TECH

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Neutronic and fuel cycle performance of LEU fuel with different means of excess reactivity control: Impact of neutron leakage and refueling scheme

Nabila

Sahadath

2022

Annals of Nuclear Energy

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Investigating the Performance and safety features of Pressurized water reactors using the burnable poisons

Cited by 16 publications

References 12 publications

The effect of control rods on the reactivity and flux distribution of BWR 4 bundle using MCNPX Code

The effect of control rods on the reactivity and flux distribution of BWR 4 bundle using MCNPX Code

Investigating core axial power distribution with multi-concentration gadolinium in PWR

Neutronic and fuel cycle performance of LEU fuel with different means of excess reactivity control: Impact of neutron leakage and refueling scheme

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