NRE 6301 - Reactor Engineering
Offered Every Fall
| Credit Hours: | 3-0-3 |
| Prerequisite: | Graduate standing in engineering or equivalent discipline |
| Course Description: | Two-phase flow, boiling heat transfer, fast reactor thermal-hydraulics, reactor thermal-hydraulics uncertainty analysis, loss-of-coolant-accidents. Reactor thermal-hydraulic accident analysis. |
| Textbook: | Richard T. Lahey
and Frederick J. Moody, The Thermal-Hydraulics of Boiling Water Reactors,
Second Edition, American Nuclear Society, 1993 |
| Instructor: | S. M. Ghiaasiaan |
| References: | Nuclear Reactor Safety Heat Transfer, O.C. Jones, ed., Hemisphere, 1981. |
| Fast Breeder Reactors, A.E. Waltar, and A.B. Reynolds, Pergamon Press, | |
| Theory manuals of current versions of TRAC-PF, RELAP5, and RETRAN computer codes. | |
| Goals: |
To introduce the students to the advanced theory and practice of nuclear reactor thermal-hydraulics analysis under normal and accident conditions. |
| Prerequisites by Topic: | Differential equations; Fluid Mechanics; Convective Heat Transfer; Thermal and Fast Nuclear Reactor Concepts |
| Topics: | Introduction |
| Introduction to Two-Phase Flow | |
| Boiling Heat Transfer | |
| Subchannel Analysis | |
| Thermal-Hydraulics of Fast Breeder Reactors | |
| Thermal-Hydraulics Uncertainty Analysis | |
| Loss-of-Coolant Accidents | |
| Review of Thermal-Hydraulics Codes Used for Reactor Accident Analysis | |
| Computer Usage: | Computations needed for homework assignments |
| Laboratory Projects: | None |
Prepared by: S. M. Ghiaasiaan
Date: 1/22/97
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Revised July 2004