Masters Theses

Abstract

"Following the Three Mile Island Unit 2 (TMI-2) disaster, the development of a diagnostic system for emergency situations in a nuclear power plant was identified as an essential research area to strengthen the safety of nuclear power plants. A real-time estimation system of vital safety parameters on the main side of a PWR (Pressurized Water Reactor) facility was investigated since precise post-event scenario estimations are thought to be a crucial component of the diagnostic system. The alarm system of the plant can detect an SB-LOCA (Small Break Loss-Of-Coolant-Accident), but there were a couple of potential long-term transient occurrences. The accident situation might get worse if the facility is not provided with the appropriate, timely protection it required. It is necessary to correctly predict the size and position of a tiny break as well as important state variables inside the main side, such as the pressure, temperature, and flow rates of the various primary loops as well as the temperature distribution of the fuel rods. With the information provided, it was possible to choose the best course of action for protection. The objective of this document was to model the PUMA test facility in ATHLET to assess the thermal-hydraulic response of ATHLET. This article demonstrated and assessed ATHLET's capability to accurately forecast the minor break LOCA phenomenon after severe incidents"-- Abstract, p. iii

Advisor(s)

Schlegel, Joshua P.

Committee Member(s)

Alajo, Ayodeji Babatund
Alam, Syed

Department(s)

Nuclear Engineering and Radiation Science

Degree Name

M.S. in Nuclear Engineering

Publisher

Missouri University of Science and Technology

Publication Date

Spring 2024

Pagination

ix, 40 pages

Note about bibliography

Includes_bibliographical_references_(pages 38-39)

Rights

© 2023 Emin Fatih Ozdem, All rights reserved

Document Type

Thesis - Open Access

File Type

text

Language

English

Thesis Number

T 12343

Electronic OCLC #

1427256548

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