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Nulcear Energy and Technology

A special issue of Energies (ISSN 1996-1073). This special issue belongs to the section "B4: Nuclear Energy".

Deadline for manuscript submissions: closed (15 December 2021) | Viewed by 17178

Special Issue Editor

Prof. Dr. Changhyun Roh

E-Mail Website
Guest Editor
1. Decommissioning Technology Research Division, Korea Atomic Energy Research Institute (KAERI), 989-111 Daedukdaero, Yuseong, Daejeon 34057, Republic of Korea
2. Advanced Radiation Technology Institute (ARTI), Korea Atomic Energy Research Institute (KAERI), Jeonbuk 56212, Republic of Korea
3. Quantum Energy Chemical Engineering, University of Science and Technology, 217, Gajeong-ro, Yuseong-gu, Daejeon 34113, Republic of Korea
Interests: radiochemistry; radiation chemistry; nanomaterials; nanotechnology; nuclear energy; decommissioning and decontamination science and technology; environmental science and technology; radioactive isotopes; radiation; chemical engineering; separation technology; catalysis; biotechnology; education; sustainability; chemosensors
Special Issues, Collections and Topics in MDPI journals

Special Issue Information

Dear Colleagues,

This Special Issue of Energies covers original research, ideas, and developments in all areas of nuclear energy science and technology. Its scope embraces fundamental nuclear science and technology, nuclear materials, radiation effects in physics and chemistry, decommissioning, and environmental considerations. In addition to traditional subjects, papers dealing with new areas of science and technology that fit the broad scope and objectives of the journal are encouraged. My aim is to encourage scientists and engineers to publish their experimental and theoretical results in as much detail as possible. Therefore, there is no restriction on the length of the papers. This Special Issue publishes original papers, review articles, editorials, case reports, short communications, technical notes, and letters to editors. Authors are encouraged to submit manuscripts that bridge the gaps between research, development, and implementation. The breadth of coverage ranges from innovative technologies and systems of both applied and nuclear energy, including radiation, to the industrial and domestic use of energy, with no or a minor impact on the environment.

Prof. Dr. Changhyun Roh
Guest Editor

Manuscript Submission Information

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Published Papers (5 papers)

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Research

14 pages, 9270 KiB  
Article
Flattening of the Power Distribution in the HTGR Core with Structured Control Rods
by Michał Górkiewicz and Jerzy Cetnar
Energies 2021, 14(21), 7377; https://doi.org/10.3390/en14217377 - 5 Nov 2021
Cited by 2 | Viewed by 2220
Abstract
Control rods (CRs) have a significant influence on reactor performance. Withdrawal of a control rod leaves a region of the core significantly changed due to lack of absorber, leading to increased fission rate and later to Xe135 buildup. In this paper, an innovative [...] Read more.
Control rods (CRs) have a significant influence on reactor performance. Withdrawal of a control rod leaves a region of the core significantly changed due to lack of absorber, leading to increased fission rate and later to Xe135 buildup. In this paper, an innovative concept of structured control rods made of tungsten is studied. It is demonstrated that the radial division of control rods made of tungsten can effectively compensate for the reactivity loss during the irradiation cycle of high-temperature gas-cooled reactors (HTGRs) with a prismatic core while flattening the core power distribution. Implementation of the radial division of control rods enables an operator to reduce this effect in terms of axial power because the absorber is not completely removed from a reactor region, but its amount is reduced. The results obtained from the characteristic evolution of the reactor core for CRs with a structured design in the burnup calculation using the refined timestep scheme show a very stable core evolution with a reasonably low deviation of the power density and Xe135 concentration from the average values. It is very important that all the distributions improve with burnup. Full article
(This article belongs to the Special Issue Nulcear Energy and Technology)
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14 pages, 5026 KiB  
Article
Improved FAST Device for Inherent Safety of Oxide-Fueled Sodium-Cooled Fast Reactors
by Ahmed Amin E. Abdelhameed, Chihyung Kim and Yonghee Kim
Energies 2021, 14(15), 4610; https://doi.org/10.3390/en14154610 - 29 Jul 2021
Cited by 3 | Viewed by 2102
Abstract
The floating absorber for safety at transient (FAST) was proposed as a solution for the positive coolant temperature coefficient in sodium-cooled fast reactors (SFRs). It is designed to insert negative reactivity in the case of coolant temperature rise or coolant voiding in an [...] Read more.
The floating absorber for safety at transient (FAST) was proposed as a solution for the positive coolant temperature coefficient in sodium-cooled fast reactors (SFRs). It is designed to insert negative reactivity in the case of coolant temperature rise or coolant voiding in an inherently passive way. The use of the original FAST design showed effectiveness in protecting the reactor core during some anticipated transients without scram (ATWS) events. However, oscillation behaviors of power due to refloating of the absorber module in FAST were observed during other ATWS events. In this paper, we propose an improved FAST device (iFAST), in which a constraint is imposed on the sinking (insertion) limit of the absorber module in FAST. This provides a simple and effective solution to the power oscillation problem. Here, we focus on an oxide fuel-loaded SFR that is characterized by a more negative Doppler reactivity coefficient and higher operating temperature than the metallic-loaded SFR cores. The study is carried out for the 1000 MWth advanced burner reactor with an oxide fuel-loaded core during postulated ATWS events that are unprotected transient over power, unprotected loss of flow, and unprotected loss of the heat sink. It was found that the iFAST device has promising potentials for protecting the oxide SFR core during the various studied ATWS events. Full article
(This article belongs to the Special Issue Nulcear Energy and Technology)
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25 pages, 6079 KiB  
Article
Neutron Activation of Structural Materials of a Dry Storage System for Spent Nuclear Fuel and Implications for Radioactive Waste Management
by Se Geun Lee and Jae Hak Cheong
Energies 2020, 13(20), 5325; https://doi.org/10.3390/en13205325 - 13 Oct 2020
Cited by 3 | Viewed by 3980
Abstract
In order to estimate the radiological characteristics of disused dry storage systems for spent nuclear fuel, a stepwise framework to calculate neutron sources (ORIGEN-ARP), incident neutron flux and reaction rate (MCNPX), effective cross-section (hand calculation), and residual activity (ORIGEN-2) was established. Applicability of [...] Read more.
In order to estimate the radiological characteristics of disused dry storage systems for spent nuclear fuel, a stepwise framework to calculate neutron sources (ORIGEN-ARP), incident neutron flux and reaction rate (MCNPX), effective cross-section (hand calculation), and residual activity (ORIGEN-2) was established. Applicability of the framework was demonstrated by comparing the residual activity of a commercialized storage system, HI-STORM 100, listed in the safety analysis report and calculated in this study. For a reference case assuming an impurity-free storage system, the modified effective cross-sections were theoretically interpreted and the need for managing disused components as a radioactive waste for at least four years was demonstrated. Sensitivity analyses showed that the higher burnup induces the higher residual radioactivity, and the impurity 59Co may extend the minimum decay-in-storage period up to 51 years within the reported range of 59Co content in stainless steel. The extended long-term storage over 100 years, however, caused no significant increase in residual radioactivity. Impurity control together with appropriate decay-in-storage was proposed as an effective approach to minimize the secondary radioactive waste arising from disused dry storage systems. The results of this study could be used to optimize the decommissioning and waste management plan regarding interim storage of spent fuel. Full article
(This article belongs to the Special Issue Nulcear Energy and Technology)
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24 pages, 5011 KiB  
Article
Characteristics of Radioactive Effluent Releases from Pressurized Water Reactors after Permanent Shutdown
by Ji Su Kang and Jae Hak Cheong
Energies 2020, 13(10), 2436; https://doi.org/10.3390/en13102436 - 12 May 2020
Cited by 3 | Viewed by 3035
Abstract
In order to expand our understanding of the characteristics of radioactive effluent from nuclear power plants under decommissioning, which have not been systematically investigated, a series of source term models of radioactive effluent after permanent shutdown has been established based upon theoretical reasoning [...] Read more.
In order to expand our understanding of the characteristics of radioactive effluent from nuclear power plants under decommissioning, which have not been systematically investigated, a series of source term models of radioactive effluent after permanent shutdown has been established based upon theoretical reasoning on the design and operation features of plants and derived in terms of fifteen arguments. Comprehensive radioactive effluent data have been collected and profiled from twenty-eight decommissioning pressurized water reactors, and annual trends of effluent from each plant have been quantitatively analyzed using Mann-Kendall statistical test. In addition, the characteristics of collected effluent data have been qualitatively interpreted based upon arguments newly proposed in this study. Furthermore, potential decreasing of dilution factor for liquid effluent and its safety implications are identified. The source term models and verified characteristics of radioactive effluent after permanent shutdown developed in this study can be used for establishing more efficient discharge monitoring program for decommissioning authorization. Full article
(This article belongs to the Special Issue Nulcear Energy and Technology)
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11 pages, 3503 KiB  
Article
Colorimetric Method for Detection of Hydrazine Decomposition in Chemical Decontamination Process
by Jungsoon Park, Hee-Chul Eun, Seonbyeong Kim, Changhyun Roh and So-Jin Park
Energies 2019, 12(20), 3967; https://doi.org/10.3390/en12203967 - 18 Oct 2019
Cited by 8 | Viewed by 4717
Abstract
The aim of nuclear facility decommissioning is to make local settlements safe, sustainable and professedly acceptable. The challenges are the clean-up of the nuclear site and waste management. This means a definite promise in terms of safety and security, taking into account social [...] Read more.
The aim of nuclear facility decommissioning is to make local settlements safe, sustainable and professedly acceptable. The challenges are the clean-up of the nuclear site and waste management. This means a definite promise in terms of safety and security, taking into account social and environmental accountability. There is an essential need to develop safe and efficient methods for nuclear decommissioning. Thus, chemical decontamination technology is of great significance to the decommissioning of nuclear energy facilities. In particular, chemical decontamination technology is applicable to the pipelines and internal loop. The iron-rich oxides, such as Fe3O4 or NiOFe2O3, of a nuclear power plant should have sound decontamination follow-through and should put through a very small amount of secondary waste. It is important to be able to detect and quantify hydrazine in decontamination situations with high sensitivity and selectivity. A colorimetric assay is a technique used to determine the concentration of colored compounds in a solution. However, detecting targeted species rapidly and easily, and with high sensitivity and specificity, is still challenging. Here, the catalytic reaction of oxidants in the p-dimethylaminobenzaldehyde and hydrazine reaction is elucidated. Oxidants can catalyze the reaction of hydrazine and p-dimethylaminobenzaldehyde to form an azine complex such as p-dimethylaminobenzaldazine, with high selectivity and sensitivity within 30 min at ambient temperatures. In the absence of an oxidant such as iron or hydrogen peroxide no detectable colorimetric change was observed by the reaction of p-dimethylaminobenzaldehyde and hydrazine unless an external oxidant was present in the system. In this study, we demonstrated a colorimetric method for the sensitive detection of hydrazine decomposition in the chemical decontamination process. Furthermore, the colorimetric response was easy to monitor with the unaided eye, without any sophisticated instrumentation. This method is thus suitable for on-site detection of contamination in a nuclear facility. In addition, this colorimetric method is convenient, non-invasive, free of complex equipment, and low-cost, making it possible to analyze hydrazine in industrial nuclear facilities. The proposed method was successfully applied to the determination of hydrazine decomposition in the nuclear decontamination process. Full article
(This article belongs to the Special Issue Nulcear Energy and Technology)
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