Published November 2008 | Version v1
Journal article

The Thermal-Hydraulic model for the pebble bed modular reactor (PBMR) plant operator training simulator system

  • 1. Pebble Bed Modular Reactor (Proprietary) Limited, Die Anker Building, Centurion 0046 (South Africa)
  • 2. GSE Systems, Inc., 7133 Rutherford Suite 200, Baltimore, MD 21244 (United States)

Description

This paper provides a discussion of the model development status and verification efforts for the Reactor Core Thermal-Hydraulic model developed for the full-scope plant Operator Training Simulator System of the Pebble Bed Modular Reactor (PBMR). Due to the First of a Kind Engineering nature and lack of reference plant data, model verification has mainly been focused on benchmarking the model configurations against test cases performed by PBMR design analysis codes, i.e. TINTE, VSOP and FLOWNEX. As a first step, due to the symmetrical physical nature of the PBMR core, a two-dimensional (2D) model configuration in radial and axial directions (axial-symmetry) was developed. The design was subsequently extended to a three-dimensional (3D) configuration. Through the use of cross-flow and cross-conduction links, three nearly identical 2D configurations were glued together to form this 3D model configuration. To date, the 3D configuration represents the most comprehensive model to simulate the PBMR core thermo-hydraulics. This paper concludes with the verification of thermodynamic and heat-transfer properties of two steady state (100% and 40% power) conditions between the 3D Reactor Core Thermal-Hydraulic model and the available FLOWNEX and TINTE design code analysis. The transient operations between these two power levels are also discussed.

Part of:
3. International Topical Meeting on High Temperature Reactor Technology

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2007.12.022;
PII
S0029-5493(08)00142-8;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
238
Journal Issue
11
Journal Page Range
p. 3102-3113
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
3. international topical meeting on high temperature reactor technology
Acronym
HTR-2006
Dates
1-5 Oct 2006
Place
Johannesburg (South Africa)

Optional Information

Copyright
Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.