Abstract

In the past few years, developments in the APOLLO3® deterministic code have mainly been devoted to Fast Reactor applications. In this paper, we investigate the possibility of using some of these methods to build an accurate two-step calculation scheme for commercial Pressurized Water Reactors, with application to the BEAVRS benchmark at hot zero power conditions of cycle 1. Our objective is to assess the performances of the best “standard” calculation currently possible with APOLLO3® and to have a starting point for the development of improved transport solvers and innovative calculation schemes. At the lattice level, we show that the subgroup method using the REL383 energy mesh, associated with a MOC flux calculation, provides accurate results on different clusters of 3x3 cells with UOX and MOX fuel, including a heterogeneity at the center (guide-tube full of water or with common absorbers Ag-In-Cd or B4C inserted, and mixed uranium-gadolinium oxide fuel). These good results have been confirmed on BEAVRS assembly, rods in and rods out. At the core level, 20-group 3D calculations with the MINARET Sn solver have been performed at the cell level to analyze BEAVRS Hot Zero Power results (reactivity, power map, and control rods worths). Results are rather satisfactory, considering the low computing cost, but the power map prediction needs to be improved.

Highlights

  • We investigate the possibility of using some of these methods to build an accurate two-step calculation scheme for commercial Pressurized Water Reactors, with application to the BEAVRS benchmark at hot zero power conditions of cycle 1

  • The results reported in [7] show that the subgroup method using the REL383 energy mesh followed by a MOC flux calculation provides accurate results in various situations and can be considered as a reference for LWR lattice calculations

  • Our objective is to evaluate the performances of the best “classical” calculation currently possible with APOLLO3® and to have a starting point for the development of improved transport solvers and innovative calculation schemes

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Summary

INTRODUCTION

In the past few years, developments in the APOLLO3® code [1] have mainly been devoted to Fast Reactor applications: x At the lattice level: subgroup and Tone’s self-shielding methods [2], exact B-heterogeneous leakage model and flux moments weighting homogenization [3], 3D TDT-MOC solver [4] and 2D-MOC/1DSn fusion method for 3D assembly homogenization [5], x At the core level: unstructured Sn solver MINARET allowing to perform Sn 3D transport calculations on heterogeneous geometries [6]. We investigate the possibility of using some of these methods to build an accurate two-step calculation scheme for commercial Pressurized Water Reactors, with application to the BEAVRS benchmark at hot zero power conditions of cycle 1. The second chapter first presents the two-step APOLLO3-LWR calculation scheme as applied to BEAVRS

Lattice Step
Core Calculation
Clusters Fissile-Absorber
BEAVRS Assemblies
Reactivity
Control rod bank worth
Power distribution
Findings
CONCLUSIONS
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