Dynamic feedback characteristics of Ghana Research Reactor-1

Akaho, E.H.K.; Anim-Sampong, S.; Maakuu, B.T.; Dodoo-Amoo, D.N.A.

doi:10.4314/jgsa.v2i3.17896

Cited by 9 publications

(4 citation statements)

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“…• The insights from GHARR-1's PPF behavior have significant implications for future reactor designs [5], and can inform policy on reactor operation and extension [22].…”

Section: Broader Implications For Reactor Design and Policymentioning

confidence: 99%

Assessment of Axial Power Peaking Factors in GHARR-1 LEU Core: A Decadal Simulation Analysis

Ahiave,

Ampomah-Amoako,

Abrefah

et al. 2024

WJNST

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This study aims to thoroughly investigate the axial power peaking factors (PPF) within the low-enriched uranium (LEU) core of the Ghana Research Reactor-1 (GHARR-1). This study uses advanced simulation tools, like the MCNPX code for analysing neutron behavior and the PARET/ANL code for understanding power variations, to get a clearer picture of the reactor's performance. The analysis covers the initial six years of GHARR-1's operation and includes projections for its whole 60-year lifespan. We closely observed the patterns of both the highest and average PPFs at 21 axial nodes, with measurements taken every ten years. The findings of this study reveal important patterns in power distribution within the core, which are essential for improving the safety regulations and fuel management techniques of the reactor. We provide a meticulous approach, extensive data, and an analysis of the findings, highlighting the significance of continuous monitoring and analysis for proactive management of nuclear reactors. The findings of this study not only enhance our comprehension of nuclear reactor safety but also carry significant ramifications for sustainable energy progress in Ghana and the wider global context. Nuclear engineering is essential in tackling global concerns, such as the demand for clean and dependable energy sources. Research on optimising nuclear reactors, particularly in terms of safety and efficiency, is crucial for the ongoing advancement and acceptance of nuclear energy.

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“…• The insights from GHARR-1's PPF behavior have significant implications for future reactor designs [5], and can inform policy on reactor operation and extension [22].…”

Section: Broader Implications For Reactor Design and Policymentioning

confidence: 99%

Assessment of Axial Power Peaking Factors in GHARR-1 LEU Core: A Decadal Simulation Analysis

Ahiave,

Ampomah-Amoako,

Abrefah

et al. 2024

WJNST

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“…To assist IAEA Member States in understanding ageing of SSCs important to safety and in effective ageing management of these SSCs, the IAEA in 1989 initiated a project on safety aspects of NPP ageing. The Safety Practices Publication Data Collection and Record Keeping for the Management of Nuclear Power Plant Ageing provides information on data requirements and a system for data collection and record keeping for the Ghana MNSR (Akaho, Anim-Sampong and Dodoo-Amoo, 1995). This project integrates information on the evaluation and management of safety aspects of reactor ageing generated by Member States into a common knowledge base, and derives guidance and assists Member States in the application of this guidance (International Atomic Energy Agency, 1990, 1991, 1992, 1992b, 1999Kang and Moore, 2013).…”

Section: Iaea Guidelines and Their Use In Gharr-1mentioning

confidence: 99%

A Review of Ghana Research Reactor-1 (GHARR-1) Component Aging Degradation Problems and Ways of Mitigation

Ameyaw

Abrefah²,

Amponsah-Abu³

2018

EREM

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GHARR-1 facility is a miniature neutron source reactor with a rated power of 30 kW. GHARR-1 was commissioned on 8 th March, 1995. The facility has been operating using the microcomputer closed loop system (MCCLS) and the control console (CC) for 19 years. Age-related degradation effects in safety-related systems of nuclear reactors are managed to prevent safety margins from eroding below the acceptable limits provided in reactors design. This paper, therefore, provides an update on managing the safety aspects of ageing of structures, systems, and components (SSC) of GHARR-1. Managing the safety aspects of research reactor ageing requires a proactive, systematic, and integrated ageing management approach for the coordination of all activities relating to control, monitoring, and mitigation of ageing degradation of SSC through the life cycle of GHARR-1. This paper outlines the ageing management programme and mitigation practices. Strategies for the ageing management include periodic safety reviews, design features for components and unit replacement, and succession planning. Information sharing with other operating organizations is one of the means considered by GHARR-1 to attain excellence. This paper again concisely reviews and integrates information developed by other ageing management studies and other available information related to understanding and managing age-related degradation effects.

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“…Ghana Research Reactor-1 (GHARR-1) is a Miniature Neutron Source Reactor (MNSR) used mainly for Neutron Activation Analysis (NAA), education, and training [1,2].…”

Section: Introductionmentioning

confidence: 99%

Failure Mode and Effect Analysis for a Programmable Logic Controller-Based Control Unit for a Miniature Neutron Source Reactor Pneumatic Transfer System

Obeng

Amponsah-Abu

Nayrko

et al. 2021

Journal of Electrical and Computer Engineering

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The Pneumatic Transfer System (PTS) is an auxiliary system of Ghana Research Reactor-1 (GHARR-1) used to transfer the sample capsule in and out of the reactor irradiation sites. The PTS′ controller unit design and construction was carried out because the original transfer system was not designed to operate in Cyclic Neutron Activation Analysis (CNAA). To address these situations, a Programmable Logic Controller (PLC) has been used to design and construct a control unit to facilitate a CNAA application for GHARR-1. The design has been simulated successfully using LOGO! Soft Comfort software, version 8. A Failure Mode and Effect Analysis (FMEA) was conducted on the PTS Control Unit (PTSCU) to evaluate and document, by item failure mode analysis, the potential impact of each functional or hardware failure of the control unit, personnel and system safety, system performance, maintainability, and maintenance requirements. Each potential failure is ranked by the severity of its effect so that appropriate corrective actions can be taken to eliminate or control the high-risk items. The result obtained upon the analysis shows that the likelihood of occurrence of failures, detection, and severity on the control unit is low per the risk priority number. The paper outlines the severity classification and description used in FMEA, the likelihood of detecting various failures of components, and failure causes and effect.

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Dynamic feedback characteristics of Ghana Research Reactor-1

Cited by 9 publications

References 0 publications

Assessment of Axial Power Peaking Factors in GHARR-1 LEU Core: A Decadal Simulation Analysis

Assessment of Axial Power Peaking Factors in GHARR-1 LEU Core: A Decadal Simulation Analysis

A Review of Ghana Research Reactor-1 (GHARR-1) Component Aging Degradation Problems and Ways of Mitigation

Failure Mode and Effect Analysis for a Programmable Logic Controller-Based Control Unit for a Miniature Neutron Source Reactor Pneumatic Transfer System

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