Abstract

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.

Highlights

  • The Four-Bundle Lattice, known as the F-Lattice, is an innovative design that reduces the total number of control blades employed in the Boiling Water Reactor (BWR) design

  • When F-Lattice is utilized in the ESBWR (Economically Simplified Boiling Water Reactor) design, only half the number of control rods is required in the core

  • The effective multiplication factor results for the F-Lattice with ­B4C and C are obtained by MCNPX and they are compared with SCALE5.1 K-eff results as shown in the previous Table 2

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Summary

Introduction

The Four-Bundle Lattice, known as the F-Lattice, is an innovative design that reduces the total number of control blades employed in the Boiling Water Reactor (BWR) design. This Lattice type utilizes a staggered row configuration for the control blades. When F-Lattice is utilized in the ESBWR (Economically Simplified Boiling Water Reactor) design, only half the number of control rods is required in the core. There would have been approximately half the number of control rod related components requiring maintenance or posing the risk of failure This is accompanied by a reduction in cost and an increase in safety; the two key goals of all design modifications in a nuclear reactor. This has been recently confirmed for an advanced BWR with a published core design which had been modeled by experts in reactor p­ hysics[8]

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