Sensitivity and Uncertainty Information Incorporated Loss of Flow Accident Analyses for Research Reactors

2021 ◽  
Author(s):  
Tao Liu ◽  
Zeyun Wu
Keyword(s):  
Research Reactors ◽  
Uncertainty Information

Sensitivity and Uncertainty Information Incorporated Loss of Flow Accident Analyses for Research Reactors

2020 ◽  
Author(s):  
Tao Liu ◽  
Zeyun Wu
Keyword(s):  
Research Reactor ◽  
Safety Analysis ◽  
Primary Objective ◽  
Analysis Procedure ◽  
System Level ◽  
Normal Operation ◽  
Reactor Model ◽  
Research Reactors ◽  
Design Basis ◽  
Uncertainty Information

Abstract This paper outlines a system level safety analysis procedure for research reactors incorporating sensitivity and uncertainty components. The protected loss of flow (LOF) accident was selected as an exemplified design basis accident to demonstrate the analysis procedure. The conceptual NIST (National Institute of Standards and Technology) horizontally split-core based research reactor was adopted as a research reactor model in the study. Two system level dynamics codes, RELAP5-3D and PARET, were employed in this work in a comparison study manner. The primary objective of the present work is to demonstrate the analysis capability of integrating sensitivity and uncertainty information in addition to traditional predictions of the system code models for the study of the thermal-hydraulics (T/H) safety characteristics of research reactors under accidental transient scenarios. The canonical transient predictions on the LOF accident yielded from the two system codes mentioned above have demonstrated some noticeable yet acceptable discrepancies. To better understand the discrepancies observed in the simulations, sensitivity and uncertainty analyses were performed by coupling the RELAP5-3D model and the data analytic engines provided by the RAVEN framework developed by INL. The sensitivity information reveals the significances of key figure of merits such as the peak cladding temperature varies with different boundary and initial parameters in both normal operation and design basis transients. The uncertainty analysis informs the deviations of the responses contributed by the errors of various input components. Both the sensitivity and uncertainty information will be incorporated into a safety analysis framework as part of the safety characteristic predictions delivered by the framework.

ACCELERATED LIFE TESTING OF COMPONENTS OF NUCLEAR RESEARCH REACTORS

2016 ◽  
Author(s):  
Vanderley Vasconcelos ◽  
WELLINGTON SOARES ◽  
Antonio Carlos Lopes da Costa ◽  
Raíssa Oliveira Marques
Keyword(s):  
Nuclear Research ◽  
Accelerated Life Testing ◽  
Life Testing ◽  
Research Reactors ◽  
Accelerated Life

Performance analyses of the communication networks of a modern supervision and control system of research reactors

Kerntechnik ◽  
2009 ◽  
Vol 74 (1-2) ◽  
pp. 42-46
Author(s):  
E. I. El-Madbouly ◽  
M. K. Shaat ◽  
A. M. Shokr ◽  
G. H. Elrefaei
Keyword(s):  
Control System ◽  
Communication Networks ◽  
Research Reactors ◽  
Performance Analyses ◽  
And Control

scholarly journals Experience of long-term U–Al fuel performance in research reactors with low energy generation

2020 ◽  
Vol 1689 ◽  
pp. 012024
Author(s):  
V P Alferov ◽  
N I Geraskin ◽  
A F Kozhin ◽  
A E Kruglikov ◽  
S A Ozherelev ◽  
...  
Keyword(s):  
Energy Generation ◽  
Low Energy ◽  
Fuel Performance ◽  
Research Reactors
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