Utilization Of Nuclear Power Research Articles

Scenario analysis of the Indonesia carbon tax impact on carbon emissions using system dynamics modeling and STIRPAT model

This study aims to develop a system dynamic (SD) forecasting model based on the STIRPAT model to forecast the effect of an IDR 30 per kg CO2e carbon tax on carbon emissions, estimate future carbon emissions under ten scenarios, without and with the carbon tax, and estimate the environmental Kuznets curve (EKC) to predict Indonesia’s carbon emission peak. Carbon emission drivers in this study are decomposed into several factors, namely energy structure, energy intensity, industrial structure, GDP per capita, population, and fixed-asset investment. This study included nuclear power utilization starting in 2038. The research gaps addressed by this study compared to previous research are (1) use of the ex-ante approach, (2) inclusion of nuclear power plants, (3) testing the EKC hypothesis, and (4) contribution to government policy. The simulation results show that under the carbon tax, carbon emissions can be reduced by improving renewable energy structures, adjusting industrial structures to green businesses, and emphasizing fixed asset investment more environmentally friendly. Moreover, the result approved the EKC hypothesis. It shows an inverse U-shaped curve between GDP per capita and CO2 emissions in Indonesia. Indonesia’s fastest carbon emission peak is under scenario seven and is expected in 2040. Although an IDR 30 per kg CO2e carbon tax and nuclear power will take decades to reduce carbon emissions, the carbon tax can still be a reference and has advantages to implement. This result can be a good beginning step for Indonesia, which has yet to gain experience with a carbon tax that can be implemented immediately and is helpful to decision-makers in putting into practice sensible measures to attain Indonesia’s carbon emission peaking. This research provides actionable insights internationally on carbon tax policies, nuclear energy adoption, EKC dynamics, global policy implications, and fostering international cooperation for carbon emission reductions.

MoS2 decorated heteroatoms doped carbon microspheres for efficient separation of uranium from wastewater

Uranium serves as a fundamental element for sustainable nuclear reactor energy. Hence, the extraction and enrichment of uranium from radioactive wastewater is of considerable significance for both nuclear power utilization and environmental protection. In this study, carbon microspheres (TAC) doped with nitrogen, phosphorus and sulfur were derived from ternary polyphosphazene. Subsequently, molybdenum disulfide (MoS2) was integrated using hydrothermal method to fabricate the TAC/MoS2 composite, which is designed for the efficient enrichment and separation of uranyl ions. Owing to the unique two-dimensional structure of MoS2 and its strong affinity towards uranyl ions, the adsorption capacity of the composite was significantly enhanced to 399.6 mg/g within 80 min at pH 5 and 298.15 K. Additionally, the composite exhibited commendable thermal stability and hydrophilicity, declaring that it is an outstanding candidate for the efficient enrichment and separation of uranyl ions. Further mechanism studies through XPS analysis and DFT calculations suggested that the vacancies introduced by MoS2 can generate electrostatic interactions and coordination effects with uranyl ions, thereby improving the adsorption performance of the composite. Due to its straightforward preparation process and exceptional adsorption performance, TAC/MoS2 possesses broad application prospects in the extraction of uranium from wastewater.

Recent progress of covalent organic frameworks in high selective separation of radionuclides

The utilization of nuclear energy power and nuclear weapon tests not only releases large amounts of radionuclides into environment, but also needs 235U as nuclear fuel for nuclear energy generation. Covalent organic frameworks (COFs) have the advantages of tunable porous structures, adjustable active sites and enough special functional groups, which assure the high selective preconcentration of target radionuclides from complex solutions. In this perspective, the selective extraction of radionuclides (U(VI) as representative cationic ion, Tc(VII) as representative anionic ion, I2 as gaseous nuclide and other nuclides) by COFs through sorption, and photocatalytic strategies are described, and the results show the high efficiency of COFs in target radionuclides removal. The perspective and challenges for the real applications of COFs in future are discussed in the end.Graphical

Study of Power Sector Reforms for Madhya Pradesh Development

AbstractThe nuclear power industry in India plays a significant role in meeting the country's energy demands and fostering economic growth. This research study explores the need for research in the context of India's nuclear power industry, specifically focusing on Madhya Pradesh (MP). The aim is to investigate the potential of nuclear energy as a clean and sustainable resource for economic development in the region. The study considers the interplay between economic growth, resource reduction, and energy consumption within the state.Highlights of the article importance of nuclear energy in India's overall energy mix and its potential for driving economic progress. The Indian nuclear power industry encompasses various sectors, including industrial, transmission, and commercial. Nuclear energy is recognized as a clean and vital economic resource, capable of providing substantial benefits to the national economy.The focus of this research is MP, the largest state in terms of nuclear power generation in India. The state's economic growth depends on several factors, including energy consumption. To achieve significant improvements in resource reduction and sustainable development, it is crucial to examine the role of nuclear power within the state's energy sector.The research study presented in this article addresses the electricity reform of the Madhya Pradesh State Electricity Board (MPSEB). By evaluating the infrastructure and recent discussions surrounding the Chutka Nuclear Power Plant project, which aims to support the energy sector in the Mandla region, this study aims to contribute to the understanding of the potential economic benefits of nuclear power in MP.The findings from this research will provide valuable insights into the relationship between nuclear energy, economic growth, and sustainable development in the Indian context. It will help policymakers, industry stakeholders, and researchers in formulating strategies and policies that promote the effective utilization of nuclear power as a catalyst for economic progress while ensuring environmental sustainability. This study ultimately contributes to the knowledge base required for harnessing the full potential of nuclear energy in India's energy landscape.

High-Level Radioactive Disposal Policy in Japan: A Sociological Appraisal

This study critically appraises the Japanese government’s high-level radioactive disposal policy by drawing on three sociological perspectives: risk society, sociology of scientific knowledge, and social acceptance. The risk society theory emphasizes that the Government of Japan and scientists under its control are pursuing nuclear power policy and repository siting within the conventional paradigm of the first modernity, which no longer aligns with the current reality of nuclear power utilization and its public awareness in Japan. Thus, a reflexive response from the policy side is essential to address the demands of a risk society. The sociology of scientific knowledge supports this view by demonstrating that, while scientists under governmental control attempt to convince the public of the safety of their geological disposal methods and the scientific validity of their siting procedures, these claims are largely a social construction of knowledge riddled with uncertainty and ambiguity about inherent environmental risks. The social acceptance standpoint also reveals a substantial bias in government measures toward ensuring distributive, procedural, and interpersonal fairness. Specifically, it critiques the heavy official reliance on monetary compensation to the host community, limited consideration of the allocation of intergenerational decision-making rights based on the reversibility principle, and the implementing agency’s one-way asymmetrical risk communication for public deliberation.

Estimation of Waste Package Inventories and Characteristics from Different Advanced Fuel Cycles

Future utilization of nuclear power may involve fuel cycles that incorporate new reactors and new fuel utilization schemes. In comparing fuel cycles in terms of their waste characteristics, many previous studies have focused on properties intrinsic to the wastes themselves: mass, radioactivity, and/or radiotoxicity. These properties do not directly inform analyses that evaluate waste management strategies, impacts, or risks. For these, information about waste packages and waste loading is critical. This paper reports on research performed to bridge the divide between nuclear fuel cycle and waste management analyses while accommodating the diversity of reactors, processes, and waste forms that could be utilized by advanced fuel cycles. An object-oriented Python code, Nuclear Waste Analysis in Python, was written to connect fuel cycle data with backend process information, thereby generating waste form characteristics and package inventories. The backend process models are informed by literature review and engineering judgment. The package is applied to the fuel cycles considered in the Fuel Cycle Evaluation and Screening (FCES) study and is benchmarked against the FCES study waste management evaluation metric data for mass and radioactivity. Hypothetical waste package inventories are reported for each fuel cycle as functions of spent fuel and high-level waste loading.

Nuclear power utilization as a future alternative energy on icebreakers

Diversified fuel types such as methanol, hydrogen, liquefied natural gas, ammonia, biofuels, have been come to fore in consideration of the limitations, regulations, environmental perception and efficient use of resources on maritime sector. NE is described as a substantial alternative energy source on the marine vessels in the sense of de-carbonization and fuel efficiency activities carried out by IMO. Although NPVs have been constructed for the merchant, navy and supply fields over the years, their numbers are few and working ranges are quite limited. NE generation techniques, reactor types, safety and security issues in case of any leakage or radiation pollution are analyzed and comparisons are performed between fossil-based fueled and NP based on icebreakers. The comparison are conducted on the basis of dimensions, resistances and operational competences by the VIKOR. NP icebreakers operated in recent years occupy a notable position in the ranking, although fossil fueled ones are most prevalent. Consequently, refueling period and emissions are the principal benefits of NPVs. Nevertheless, the use of such systems on marine vessels especially for merchant ships may come to the fore when all concerns in terms of safety, security and society are resolved since the slightest mistake can have irreversible consequences.

Using molybdenum carbiding to induce digestion of carbon in H2O2: A sustainable approach to eliminate radioactivity for hazardous graphite waste inherited from nuclear enterprise

To properly manage nuclear wastes is critical to sustainable utilization of nuclear power and environment health. Here, we show an innovative carbiding strategy for sustainable management of radioactive graphite through digestion of carbon in H2O2. The combined action of intermolecular oxidation of graphite by MoO3 and molybdenum carbiding demonstrates success in gasifying graphite and sequestrating uranium for a simulated uranium-contaminated graphite waste. The carbiding process plays a triple role: (1) converting graphite into atomic carbon digestible in H2O2, (2) generating oxalic ligands in the presence of H2O2 to favor U-precipitation, and (3) delivering oxalic ligands to coordinate to MoVI-oxo anionic species to improve sample batching capacity. We demonstrate > 99% of uranium to be sequestrated for the simulated waste with graphite matrix completely gasifying while no detectable U-migration occurred during operation. This method has further been extended to removal of surface carbon layers for graphite monolith and thus can be used to decontaminate monolithic graphite waste with emission of a minimal amount of secondary waste. We believe this work not only provides a sustainable approach to tackle the managing issue of heavily metal contaminated graphite waste, but also indicates a promising methodology toward surface decontamination for irradiated graphite in general.

A chemical‐absorption heat pump for utilization of nuclear power in high temperature industrial processes

A <scp>chemical‐absorption</scp> heat pump for utilization of nuclear power in high temperature industrial processes

Reaction: Goal-Oriented PAF Design for Uranium Extraction from Seawater

Guangshan Zhu received his BSc (1993) and PhD (1998) degrees in chemistry from Jilin University. He is now a full professor at Northeast Normal University. Driven by the demands in sustainable energy and environments, his current research interest focuses on the design and synthesis of porous aromatic frameworks for gas adsorption, separation, and uranium capture.

C[double bond, length as m-dash]N linked covalent organic framework for the efficient adsorption of iodine in vapor and solution.

Volatile nuclear wastes, such as iodine, have received worldwide attention because it poses risks to public safety and pollutes the environment. The efficient capture of radioactive iodine is of vital importance for the safe utilization of nuclear power. Herein, we report a series of stable covalent organic framework (COF) materials with high efficiency to capture radioactive iodine species. Results indicated that all COFs showed high iodine adsorption, which reached up to 5.82 g g−1 in vapor and 99.9 mg g−1 in solution, suggesting that all COFs can be an effective potential adsorbent for the removal of iodine. Furthermore, all COFs are renewable due to the excellent recycling performance. Moreover, all COFs are suitable for large-scale synthesis at room temperature, which have potential for practical applications. Theoretical calculations were also performed to analyze the relationship between iodine molecules and COFs, offering mechanisms underlying the potent adsorption abilities of COFs.

Proposal and thermoeconomic analysis of a novel combined cooling and power system using carbon dioxide as the working fluid

A novel combined cooling and power (CCP) system integrating a supercritical carbon dioxide recompression Brayton cycle with an ejector transcritical carbon dioxide refrigeration cycle (E-TCRC) is proposed to realize the effective utilization of nuclear power. In the proposed system, a portion of CO2 exiting the pre-cooler is used to drive the E-TCRC for generating cooling and recovering partial waste heat of sCO2 turbine exhaust. The mathematical model and economic model of the proposed system are established under steady-state conditions. Besides, the exergy efficiency and total product unit cost of the system are selected as the main criteria to evaluate system performance. Parametric analysis is applied to study the effects of four key parameters on the system performance. The CCP system, conventional separated cooling and power (C-SCP) system and ejector separated cooling and power (E-SCP) system are optimized by single-objective and multi-objective optimization. Single-objective optimization reveals that the exergy efficiencies of the CCP system are up to 1.08%pt (percentage point), 0.80%pt and 0.47%pt higher than those of the C-SCP system at the corresponding evaporation temperatures (−20 °C, −10 °C and 0 °C). Besides, the CCP system performs better than the E-SCP system at lower turbine inlet pressures. The multi-objective optimization shows that when the evaporation temperature increases from −20 °C to 0 °C, the total product unit cost of the CCP system decreases from 10.087 $/GJ to 9.668 $/GJ, and exergy efficiency increases from 59.25% to 60.97%.

Guidance Needed for Continued Employment of Long-term Contaminated Individuals.

Operational practices in nuclear power utilities often restrict job assignments for workers with internal contamination due to the difficulty of monitoring for new intakes and strict radioactive material controls. However, restriction of job assignments for an extended period (i.e., months to years) may be too conservative. An industry consensus on guidance in these conditions would be helpful for Radiation Safety Officers (RSOs) to allow long term contaminated workers to have less work restrictions.

Neutronics design for molten salt accelerator-driven system as TRU burner

Treatment of plutonium separated from spent fuel has been one of the most important issues in the utilization of nuclear power in Japan. This study investigates a molten salt accelerator-driven system (ADS) to transmute transuranic (TRU) nuclides to address the issue. This study proposes the MARDS (Molten salt AcceleratoR Driven System) concept which has four features: employment of chloride, no dedicated spallation target, non-contact between beam window and fuel salt and modularized core. Neutronics calculation for the MARDS concept was performed for a condition of 400 MW thermal power with 800 MeV proton beam. The calculation results showed that the maximum proton beam current was about 7 mA and about 100–120 kg plutonium could be transmuted during one-year operation. The result indicates that the MARDS concept can employ a circular accelerator instead of LINAC and transmute TRU effectively.

Optimasi Faktor Eksposi pada Pemeriksaan Radiografi Thorax menggunakan Computed Radiography

Concerning radiation safety must meet several radiation protection requirements which include justification or utilization of nuclear power, dose limitation, optimization of protection, and radiation safety. The purpose of this study was to determine the optimization of the exposure factor selection and determine the radiation dose received by the patient based on the selection of exposure factors on the thorax examination. The author observed the use of exposure factors on chest radiographic examination with a sample of 60 people. The design of this study uses the correlational method. The independent variables in this study are age, body weight, object thickness, kV, and mAs. Dependent variable exposure to radiation dose on chest examination. The conclusion of this study is the dose exposure level is influenced by age, object thickness, weight, and use of exposure factors which will then be obtained by the DRL (Diagnostic Reference Level) value.

Potential application of graphene oxide membranes in high-level liquid waste treatment

The drawbacks of current high-level liquid waste (HLLW) separation processes would bring some adverse effects on the sustainable and clean utilization of nuclear power. In this work, a novel separation method for HLLW treatment based on graphene oxide membranes (GOMs) was investigated. Effects of nitric acid concentration and membrane thickness on the permeation behaviors of typical ions through GOMs were systematically investigated. On the whole, the permeation rates were in the order: hydrogen ion, cesium ion > sodium ion > strontium ion > europium ion, uranyl ion > thorium ion, which could be well explained by size exclusion and chemical interaction. As the nitric acid concentration decreased, strong coordination cations were generally restrained from migrating through GOMs due to cations hydrolysis and deprotonation of graphene oxide sheets. Ions permeation was supposed to be a two-step process which included entrance to the membrane and intramembrane migration. Based on the favorable rejection of f-block elements, GOMs separation showed promising potential in HLLW treatment. Furthermore, a new technical route for HLLW separation was proposed which showed superiority of simplified process, low running cost, less secondary radioactive waste production.

Моделирование обезвоживания открытых систем с помощью программы RELAP5

At present, there are many software tools that have positively proven themselves for carrying out computational analysis within the framework of assessing the safety of nuclear power utilization facilities. The RELAP5 code, which is intended for carrying out improved assessment of safety, is one of such tools. Initially, its use was limited to a numerical analysis of water-heated water-cooled apparatuses. At the same time, owing to extensive capabilities of the code and stable algorithms for solving hydraulic and thermophysical problems, its application field can be made significantly broader. However, the validity of such broadening should be justified both theoretically and by verification against relevant experimental data. The computational modeling results obtained using the RELAP5 code are given. A comparison between the calculated and experimental data on heating a system operating with low heat fluxes is presented. The results obtained from computations using the RELAP5 code are compared with the results of two experiments. In the first experiment, which was carried out at atmospheric pressure, water was heated in an open thermally insulated vessel. Due to evaporation, the water level in the vessel decreased, but water boiling did not occur. As soon as the water level dropped below the thermal element heated part, the element’s wall temperature showed a sharp increase. The classical approach that was applied to modeling using the RELAP5 code showed a significant discrepancy between the experimental and calculated data. After modifying the computational model, a more adequate agreement between the calculated and experimental results was obtained. In the second experiment, the dewatered system was heated at different heater power levels. With increasing the heater power in successive steps, its temperature changed accordingly. Based on the results from comparison of the calculated and experimental data, it has been shown that the axial heat conduction mechanism has a significant effect on the heating of a partially dewatered heating element, and a method for modeling the longitudinal heat flow along the thermal element in the computations carried out using the RELAP5 code is proposed. The possibility of using the RELAP5 code for simulating a dewatered system has been demonstrated. The verification materials presented in the article contain recommendations for constructing the analysis models of systems operating with low heat fluxes, e.g., spent fuel pools at nuclear power plants.

Estimation Relationship Between Nuclear Energy Consumption and Economic Growth in Pakistan Using ARDL Approach

Background/objectives: The use of nuclear energy plays very imperative role in economic growth. Method/findings: The present study employs ARDL approach to inspect alternative and nuclear power (% of total power use) and GDP per capita (constant 2010 US$) (economic growth) in Pakistan 1971–2014. Findings: The ARDL approach suggests that the dependent variable and regressor have long-term equilibrium but they are insignificant. The outcomes also propose that, both the long-term and short term, nuclear power utilization has a non-negative impact on economic growth. As a final point, the Granger causality analysis shows a unidirectional causality between alternative and nuclear power (% of total power use) and GDP per capita (constant 2010 US$). Application: Furthermore, the ARDL test in this study suggests that nuclear energy is an effective solution to boost economic growth in Pakistan and gives useful information for policymakers.Keywords: Nuclear Power, Economic Growth, ARDL Approach, Pakistan.

Assessment of Environmental Radioactivity Surveillance Results around Korean Nuclear Power Utilization Facilities in 2017

Assessment of Environmental Radioactivity Surveillance Results around Korean Nuclear Power Utilization Facilities in 2017

Radionuclide tolerance mechanism of plants for ultraselective enrichment of low content of thorium with exceptional selectivity coefficient

Selective enriching low content of radionuclides from radioactive wastewater is a critical issue for environmentally benign utilization of nuclear power. Inspired by the tolerance mechanism of plants to radionuclides, we developed a pH-triggered ultraselective coordinative adsorption (CA) membrane. The as-prepared CA membrane featured the advantages of both coordinative adsorption and membrane separation, including ultrahigh selectivity coefficient of 1242, large capacity (80 L m−2) and short mass transfer distance. The adsorption isotherms of Th4+ on the CA membrane were well described by the Freundlich model (R2 > 0.99), and the adsorption kinetics have a good fitting by using the pseudo-second-order kinetic model (R2 > 0.99). In a continuous separation under gravity, the CA membrane was able to selectively enrich the low content of Th4+ (0.05 mmol L-1) in the presence of 700 folds (35 mmol L−1) of co-existing ions (Na+, Mg2+, K+, Ca2+, Sr2+, Cs+ and Ba2+). The exceptional extraction efficiency to Th4+ was 100%, superior to that (3.7%) of all co-existing ions. Notably, the Th4+ enriched on the CA membrane was facilely eluted by diluted HNO3 (0.1 mol L−1). The Th4+ in the eluents was enriched by up to 54 folds. The eluted CA membrane was further reused for selective enrichment of Th4+, which showed no obvious loss of selectivity and enrichment capability. Our strategy might open up a new strategy for realizing ultraselective and recyclable enrichment of low content of irradiation contaminants from wastewater.