The effect of soluble boron and gadolinium distribution on neutronic parameters of small modular reactor assembly

Mustafa, Sayed Saeed; Amin, E.

doi:10.1016/j.radphyschem.2020.108724

Cited by 10 publications

(1 citation statement)

References 2 publications

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“…The neutron flux profile is an important characteristic in determining the behavior of the reactor core and understanding the isotopic composition and the contributions from Plutonium. For these two purposes, the thermal, epithermal and flux profiles for the BWR bundle are plotted and analyzed 15 .…”

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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A PWR core power control using optimized PID controller with SQP based on control rod positioning and variable coolant flow rate

Salman,

Roman

2024

Annals of Nuclear Energy

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The effect of soluble boron and gadolinium distribution on neutronic parameters of small modular reactor assembly

Cited by 10 publications

References 2 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

A PWR core power control using optimized PID controller with SQP based on control rod positioning and variable coolant flow rate

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