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Massachusetts Institute of Technology

Thermal hydraulic performance analysis of a small integral pressurized water reactor core

Abstract

dc:description.abstract

A thermal hydraulic analysis of the International Reactor Innovative and Secure (IRIS) core has been performed. Thermal margins for steady state and a selection of Loss Of Flow Accidents have been assessed using three methodologies to account for uncertainty. The thermal hydraulic analysis has shown that the IRIS is designed with adequate thermal margin for steady state operation, the locked rotor/shaft shear accident (LR/SS) and for variants of the partial loss of flow accident. To treat uncertainties, three methods were used, ranging from conservative, deterministic methods, to more realistic and computationally demanding Monte Carlo-based methods. To facilitate the computational requirements of the thermal hydraulic analysis, a script-based interface was created for VIPRE. This scripted interface (written in Matlab) supplants the existing file-based interface. This interface allows for repeated, automatic execution of the VIPRE code on a script-modifiable input data, and parses and stores output data to disk. This endows the analyst with much greater power to use VIPRE in parametric studies, or using the Monte Carlo-based uncertainty analysis methodology. The Matlab environment also provides powerful visualization capability that greatly eases the task of data analysis.

Degree

thesis:*
Department dc:contributor.department
Massachusetts Institute of Technology. Department of Nuclear Engineering
Grantor dc:publisher
Massachusetts Institute of Technology
Year dc:date.issued
2003

Author and committee

dc:creator, dc:contributor.*
Author dc:creator
  • Blair, Stuart R. (Stuart Ryan), 1972-
Advisor dc:contributor.advisor
  • Neil E. Todreas.

Subjects

dc:subject × 1

Rights

dc:rights
Statement dc:rights
  • M.I.T. theses are protected by copyright. They may be viewed from this source for any purpose, but reproduction or distribution in any format is prohibited without written permission. See provided URL for inquiries about permission.
Language dc:language.iso
eng

Identifiers

dc:identifier.*
Handle dc:identifier.uri
http://hdl.handle.net/1721.1/17029
OAI identifier oai:identifier
oai:dspace.mit.edu:1721.1/17029

Chain of custody

source
Harvested from
MIT
Base URL
dspace.mit.edu/oai/request
Last updated
2026-07-22
Source record
OAI-PMH GetRecord
related terms
citation

Blair, Stuart R. (Stuart Ryan), 1972-. Thermal hydraulic performance analysis of a small integral pressurized water reactor core. Massachusetts Institute of Technology, 2003. http://hdl.handle.net/1721.1/17029