Nuclear Installations Research Articles

Assessment of background dose rate on non-human biota in a Mediterranean terrestrial ecosystem.

The assessment of radiological impact to the environment is usually carried out by the dose rate estimation to hypothetical entities named Reference Animals and Plants (RAPs). There are many codes to carry out this assessment, which requires the definition of a scenario and using site-specific transfer parameters when possible. Transfer parameters present a geographical bias, as they are mostly derived from temperate and arctic climate datasets, but there is a scarcity of data for Mediterranean climates. In this study, a terrestrial Mediterranean scenario was defined using the distribution of activity concentrations of anthropogenic (90Sr, 137Cs) and naturally occurring radionuclides (40K, 210Pb, 210Po, 226,228Ra, 235,238U, 232Th) in Cáceres province (Spain). Site-specific transfer factors, CRwo-media, defined as the ratio between the concentration in the whole organism and the medium (soil in this case) were considered. Dose rate assessments for terrestrial RAPs were carried out using Tier 3 in ERICA Tool, ranging 0.23-3.73µGy/h which is below the screening level of 10µGy/h. Therefore, no harmful effects are expected to occur. Internal dose rate predominates over external one because the main contributors are naturally occurring radionuclides (in most cases 40K, 226,228Ra, 210Pb, 210Po), which are mostly α-emitting radionuclides. These results can be used for the evaluation of other radiological and nuclear installations in Mediterranean climates, as they set the background dose rate.

Research on the radioactive safety of industrial steam supplied by PWR nuclear power plant

The heating source of the nuclear power steam supply installation is PWR secondary steam, but the secondary steam is potentially radioactive, and the radioactive material may migrate to the industrial steam, which goes through the leakage of the heat exchanger. Compared with the conventional industrial steam, the steam supplied by the nuclear power has potential radioactivity. Nuclear power is first introduced to produce the industrial steam, in order to analyze the specific activity and radiation effects of the industrial steam on the staffs at the user side, an analytical model of industrial steam radioactivity is developed based on the technological process of industrial steam under operating conditions, and then the exposure pathways of the staff at the user side from the industrial steam is analyzed. The specific activity of the industrial steam and the exposure dose of the staff is evaluated. According to the evaluation results, it can be seen that the dose to staff caused by the industrial steam is far smaller than the radiation impact on the public caused by the nuclear power plant, and can meet the requirements of relevant regulations and standards. Therefore from the radiation safety point of view, the industrial steam supplied by the nuclear power steam supply installation is safe and acceptable for industrial use.

Evaluation of the unavailability of the primary circuit of Triga SSR reactor, importance factors and risk criteria for its components

Abstract Probabilistic Safety Assessment is a tool for improving a nuclear installation and its safety in all its function phases. PSA provides a methodical way of identifying sequences resulting from a wide range of initiating events concerning an accident, and includes systematic and realistic determination of accident frequencies and their consequences. This paper analyzes the unavailability of the TRIGA SSR reactor primary circuit, obtaining the system unavailability value, identifying main contributors to system failure, and calculating risk importance factors. Two cases were considered: one without considering Common Cause Failure (CCF) in the developed fault tree, and the second considering CCF on pumps and heat exchangers lines. The aim was to assess their influence on the primary system’s unavailability. Two importance factors, Fussell–Vesely and Risk Achievement Worth, were employed to identify components with a strong impact on the risk (probability of system failure). These factors aid in enhancing maintenance activities and testing. The analysis utilized the EDFT code, part of the PSAMAN code package developed in SCN-Pitesti.

The impact of national policies on Europe-wide power system transition towards net-zero 2050

This research aims to investigate the potential impact of national policies on the attainment of Europe's goal of achieving net-zero greenhouse gas emissions by 2050. Specifically, it analyses the effects of policies on the power sector, by evaluating capacity expansion portfolios, import reliance, and costs by 2050. A linear programming model, the IESA-EUPS, is utilized to optimize the expansion and operation of the power system, considering 28 nodes and hourly temporal resolution. The study includes five scenarios from 2020 to 2050, with varying levels of biomass and nuclear penetration based on existing member state policies. Results show that by 2050, changes mainly occur in the interplay between firm capacities and cross-border transmission levels. Limiting biomass can significantly increase nuclear energy generation, while enforcing all policies leads to a 40 % rise in cross-border transmission by 2050, due to imbalances between countries. Some member states, such as Spain and Finland, are less affected, whereas others are heavily reliant on firm nuclear capacities. Western European countries with strict biomass and nuclear restrictions may see a boost in nuclear installations in countries allowing it. Member states without both nuclear and biomass may rely more on variable renewables, resulting in surplus electricity and increased LCOE.

The protection of nuclear installations in time of armed conflict – Old rules, new challenges

AbstractIn 2022, for the first time in some while, the public around the world was confronted with an armed conflict between states, which directly involved a nuclear facility, specifically a nuclear power plant in operation. Unfortunately, the situation following Russia's armed attack on Ukraine on 24 February 2022 and the acts of war around the Zaporizhzhya nuclear power plant once again draw attention to the need to protect nuclear facilities during armed conflicts. Therefore, this paper reviews the relevant rules of public international law and scrutinizes the norms that have been established through international legislation and soft law mechanisms to protect and guarantee the nuclear safety and security of nuclear installations.

How Does Nuclear Energy Affect Environmental Pollution? Evidence from the United States

Research Originality: Nuclear power plant installation activities, which have gained momentum since the 1970s, have made the use of nuclear energy widespread, and especially the US ranks first in the world in the nuclear energy use. This article contributes to the existing literature on environmental economics by incorporating environmental technologies and globalization into the investigation of the impact of nuclear energy on environmental pollution. Research Objectives: The aim of this study is to analyze the effects of nuclear energy consumption, environmental technologies and globalization on environmental pollution in the US.Research Methods: The paper use ARDL approach with the data of 1970-2018 period. Empirical Results: According to the findings, nuclear energy consumption negatively affects environmental quality in the US both in the short and long run. On the contrary, while environment-related technologies contribute positively to environmental quality with a reducing effect on carbon footprint in the long run. Also, globalization has an insignificant effect on environment in both short and long run.Implications: It is thought that environmental quality will improve as a result of supporting environmental technologies and exchanging nuclear energy with renewable energy sources in the US.JEL Classification: Q43, C32How to Cite:Atay Polat, M., Savranlar, B., Arslan, F. (2024). How Does Nuclear Energy Affect Environmental Pollution? Evidence from US. Etikonomi, 23(2), 511 – 526. https://doi.org/10.15408/etk.v23i2.37692.

Uncertainty propagation from crustal geologies to rock-site ground motion with a Fourier Neural Operator

Seismic hazard analyses in the area of a nuclear installation must account for a large number of uncertainties, including limited geological knowledge. Combining the accuracy of physics-based simulations with the expressivity of deep neural networks can help to quantify the influence of crustal geological uncertainties on surface ground motion. This work uses a Factorised Fourier Neural Operator (F-FNO) to learn the relationship between 3D crustal heterogeneous geologies and time-dependent wavefields at the Earth’s surface up to a 5 Hz maximal frequency. The F-FNO is pretrained on a generic database and then, fine-tuned with only 250 samples targeted to the Le Teil region (South-Eastern France). The F-FNO correctly predicts the wave arrival times and the main wavefronts. As quantified by Goodness-Of-Fit (GOF) criteria, 83% of predictions have excellent phase GOF and 75% have very good envelope GOF. The Peak Ground Velocity and Pseudo-Spectral Acceleration are also accurate, especially for geologies with low-to-moderate heterogeneities. Thanks to the F-FNO speed, ground motion distributions can be easily computed and provide safety margins compared to 1D simulations. These results show that the F-FNO is an efficient surrogate model to quantify the range of ground motion a nuclear installation could face in the presence of geological uncertainties.

Trends and Perspectives on Nuclear Waste Management: Recovering, Recycling, and Reusing

This paper focuses on the highly radioactive, long-lasting nuclear waste produced by the currently operating fission reactors and on the sensitive issue of spent fuel reprocessing. Also included is a short description of the fission process and a detailed analysis of the more hazardous radioisotopes produced either by secondary reactions occurring in the nuclear installations or by decay of the fission fragments. The review provides an overview of the strategies presently adopted to minimize the harmfulness of the nuclear waste to be disposed, with a focus on the development and implementation of methodologies for the spent fuel treatments. The partitioning-conditioning and partitioning-transmutation options are analyzed as possible solutions to decrease the presence of long-lived highly radioactive isotopes. Also discussed are the chemical/physical approaches proposed for the recycling of the spent fuel and for the reusing of some technologically relevant isotopes in industrial and pharmaceutical areas. A brief indication is given of the opportunities offered by innovative types of reactors and/or of new fuel cycles to solve the issues presently associated with radioactive waste.

Design of a Facility for Simultaneous Irradiation with Two Ion Beams based on the HIPR Accelerator for Simulations Neutron Influence

Ion accelerator facility is a powerful tool to simulate neutron irradiation effects in reactor materials. Defects in the crystal lattice arise and the accumulation of transmutation products (helium and hydrogen) occurs in the structure of the material under the action of neutrons in the structural materials of nuclear installations. At Kurchatov Complex for Theoretical and Experimental Physics the heavy ion accelerator HIPr (heavy ion prototype) is used to simulate radiation damage in steels and alloys using a 5.6 MeV Fe2+ ion beam. The second beam line is designed at the HIPr facility to simultaneously implant helium (or hydrogen) into the region of defects. The second beam line provides a beam of helium ions with energy up to 300 keV. The report presents a description of second beam line design and a status of construction the second beam line.

Non-Destructive Inspection of Additively Manufactured Classified Components in a Nuclear Installation

Non-Destructive Inspection of Additively Manufactured Classified Components in a Nuclear Installation

Stabilized voltage source inverter for sensitive loads in nuclear installations

The present paper proposes a novel design of a stabilized single-phase voltage-source inverter with pure sinusoidal output voltage for photovoltaic systems employed for feeding sensitive loads in nuclear installations. Such types of loads require a voltage source with quite stabilized magnitude and frequency and pure sinusoidal shape that is free from higher-order harmonics. The inverter is based on an H-bridge four insulated gate bipolar transistors (IGBTs) with gate drivers and optocoupler isolators. A control system based on a fast DSP unit and a microcontroller is designed for cancelation of the higher-order harmonics to produce a pure sinusoidal output with almost zero total harmonic distortion (THD). The sinusoidal purity, frequency and magnitude stabilization are achieved through pulse width modulation (PWM) controlled by a fast-response feedback system that measures the time wave form of the output voltage applied to the load and then calculates the THD, frequency and amplitude. The sinusoidal shaping is performed with aid of a sinusoidal shaping filter (SSF) to fasten the operation of higher-order harmonic cancellation. The frequency measurement is achieved through a frequency counter whereas the amplitude measurement is carried out through a differential amplifier that amplifies the difference between the output voltage of the inverter (while being applied to the load) and reference voltage that determines the desired amplitude. A prototype of the entire system of the proposed voltage-source inverter is fabricated for experimental evaluation of its performance. It is shown through simulation and experimental work that the proposed control system of the inverter output voltage is able to stabilize both the amplitude and frequency of the voltage applied to the load irrespective of the load impedance. Also, it is shown that the THD of the output voltage is -57dB\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$-57 \ ext{ dB}$$\\end{document} (0.00025%\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$0.00025 \\%$$\\end{document}), which is almost zero. Moreover, the switching losses are considerably reduced and can be negligible owing to the use of the appropriate IGBTs. The efficiency of the proposed inverter is obtained by simulation taking into account all types of losses. Also, the dependence of the inverter efficiency on the load current is investigated. The average efficiency of the proposed voltage-source inverter is shown to be higher than 97%\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$97\\%$$\\end{document}.

Impact of differences between the Nuclear Law Act and the Vienna Convention on Civil Liability for Nuclear Damage on the Terms and Conditions of Nuclear Civil Liability Insurance2nd Part

This article is the second part of the publication with the same title, which appeared in the issue no. 4/2023 of the “Insurance Law”. The first part discussed selected differences in the regulation of civil liability of the operator of a nuclear installation for nuclear personal injury between the Nuclear Law Act and the Vienna Convention. Those included the definition of nuclear personal injury, the limitation period for claims for such injury and the rules for seeking compensation thereof. The Vienna Convention sets minimum protection standards in the event of nuclear damage, which has served as a benchmark for developing the principle of civil liability insurance of the operator of a nuclear installation for nuclear damage.The second part of the article deals with practical issues and provides a summary of the most crucial information concerning nuclear insurance market. It clarifies the notion of a nuclear insurer and their available insurance options. It also discusses the major elements of the civil liability protection for nuclear damage which differ from the rules of the insured’s civil liability specified by law. Finally, it addresses obstacles which may hinder the offering of this type of insurance as compulsory insurance under national legislation. This Article concerns solely the rules for civil liability for nuclear personal injury suffered as a result of operating the nuclear power plant. Insurance aspects related to the transport of nuclear material from nuclear facilities, the operation of research reactors and radioactive waste repositories have been omitted.

Radiation dose assessments for generic nuclear power plants part I: Routine operation

The main task of the site evaluation report for nuclear installation concerning nuclear safety is the protection of the public and environment from the radiological consequences of radioactive releases in both cases of normal operation and accident conditions. The atmosphere is the most important pathway to be considered in the assessment of the environmental impact of radioactive materials released from nuclear facilities. The present study is a comprehensive investigation of environmental assessments for the dose calculation model resulting from routine operation NPPs of 1000 Mw (e). The procedure consists of different parts, beginning with the manipulation of collected meteorological data such as wind speed and direction, temperature, incoming solar radiation and utilizing a set of empirical formulae for evaluating night solar radiation emitted from the ground, and then evaluating hourly stability classes and joint frequency distribution of winds by developing code. The dilution factor was evaluated using computer code (XOQDOQ code). Finally, the radiation dose assessments resulting from the routine operation of NPPs were calculated. The processes are adapted with IAEA recommendations documents, safety guides, and ICRP recommendations. The results reveal that there is no detectable value that affects the people surrounding the site nor the environmental area concerning low population zone or exclusion area.

Radiation resistance and durability against thermal regeneration cycles of Ag-ETS-10 and Ag-ZSM-5 for collecting radioxenon

Efficient porous adsorbents are crucial for: the mitigation of radioxenon emissions from nuclear installations, the production of Xe and the detection of clandestine nuclear weapon tests. Silver-exchanged zeolites or alike, specifically Ag-ZSM-5 and Ag-ETS-10, are promising candidates for these applications. However, knowledge on their radiation resistance is lacking and further research is necessary on their durability against thermal regeneration cycles. The radiation resistance was investigated for the first time by in situ irradiation with 133Xe up to about 100 MGy on Ag-ETS-10 and Ag-ZSM-5. In parallel, the durability of non-irradiated samples against at least 43 thermal regeneration cycles was investigated on both adsorbents. Fresh, irradiated and thermally regenerated samples were analyzed using different characterization techniques. The characterizations, and more specifically Xe adsorption at 296 K, did not show particular alterations due to the irradiation and thermal regeneration cycles. This is a major step forward for more efficient radioxenon trapping as it proves that both adsorbents can be used up to these irradiation levels and withstand 43 thermal regeneration cycles without any significant loss of Xe adsorption performance. Noteworthily, peak shifting and broadening were observed in the 29Si NMR signals of irradiated Ag-ETS-10 due to the paramagnetic 133Cs decay product.

Fire-induced flows for complex fire scenarios in a mechanically ventilated two-storey structure

This work deals with smoke propagation through a multi-compartment assembly in case of a fire event in a nuclear installation. The scientific issues are the understanding of flows involving two modes of propagation (vent and doorway), together with the role of mechanical ventilation and oxygen backflows to the fire. The study is based on the analysis of two scenarios reproduced experimentally at large scale and simulated numerically. The main outcomes concern the comparison of the flow at a doorway and at a vent, the consequence of the smoke propagation for thermal stratification and the combined effect of the fire heat release rate and mechanical ventilation. The results highlight the performance of computational fluid dynamics simulations in predicting these complex scenarios. Low-velocity flow zones are identified, enabling the structure of these flows and their amplitudes to be quantified. This information provides new insights to improve fire risk assessment in nuclear facilities.

Release of Radioactive Particles to the Environment.

When environmental impact and risks associated with radioactive contamination of ecosystems are assessed, the source term and deposition must be linked to ecosystem transfer, biological uptake and effects in exposed organisms. Thus, a well-defined source term is the starting point for transport, dose, impact and risk models. After the Chornobyl accident, 3-4 tons of spent nuclear fuel were released and radioactive particles were important ingrediencies of the actual source term. As Chornobyl particles were observed in many European countries, some scientists suggested that radioactive particles were "a peculiarity of the Chornobyl accident." In contrast, research over the years has shown that a major fraction of refractory elements such as uranium (U) and plutonium (Pu) released to the environment has been released as particles following a series of past events such as nuclear weapons tests, non-criticality accidents involving nuclear weapons, military use of depleted uranium ammunition, and nuclear reactor accidents. Radioactive particles and colloids have also been observed in discharges from nuclear installations to rivers or to regional seas and are associated with nuclear waste dumped at sea. Furthermore, radioactive particles have been identified at uranium mining and tailing sites as well as at other NORM sites such as phosphate or oil and gas industrial facilities. Research has also demonstrated that particle characteristics such as elemental composition depend on the emitting source, while characteristics such as size distribution, structure, and oxidation state influencing ecosystem transfer will also depend on the release scenarios. Thus, access to advanced particle characteristic techniques is essential within radioecology. After deposition, localized heterogeneities such as particles will be unevenly distributed in the environment. Thus, inventories can be underestimated, and impact and risk assessments of particle contaminated areas may suffer from unacceptable large uncertainties if radioactive particles are ignored. The present paper will focus on key sources contributing to the release of radioactive particles to the environments, as well as linking particle characteristics to ecosystem behavior and potential biological effects.

Analisis Regulasi Manajemen Sistem Keselamatan Instalasi Nuklir dalam Mewujudkan Ketahanan Energi Indonesia

The rising energy demand in Indonesia has led to the planning of Nuclear Power Plants (NPP) as a sustainable solution, with implementation targeted around 2030. The government has emphasized the need for strict regulations, especially in safety management, reinforced by lessons from the Fukushima incident in Japan. This study underscores the critical role of regulatory analysis in the safety management of nuclear installations, which is essential for achieving energy security in Indonesia. By evaluating regulatory design and management system implementation, the research aims to identify key steps to support a safety culture in nuclear installations. Adopting a qualitative approach focused on policy analysis, this study evaluates aspects of Safety Management System Regulations in Nuclear Installations for Indonesia's Energy Security. The findings highlight the importance of structured management systems to enhance nuclear safety, providing a solid foundation for energy security. Strengthening regulations and implementing a systematic approach will ensure that Indonesia’s nuclear installations meet high safety standards, contributing positively to the country’s energy security.

Review of Construction Risks in a Nuclear Power Plant Environment

Abstract Everything in the world is about risk, from individual decisions to global manipulations, which is of fundamental importance in a nuclear power plant environment. The question is whether, in a given situation, this risk is acceptable or no longer acceptable. In some respects, the risk analysis applied to construction projects differs from the risk analysis applied to nuclear installations. For nuclear installations, the risk as such is primarily nuclear risk. In view of this, for investments involving a nuclear installation, the risk analysis to be carried out must be carried out at two separate levels. The first level is the traditional construction risk analysis, and then as a second level, each risk item should be classified from a nuclear risk point of view. In this study, the nuclear exposure of construction risks will be presented.

РИСК СМЕРТНОСТИ ОТ ОСНОВНЫХ ПАТОЛОГИЙ ВСЛЕДСТВИЕ ПАССИВНОГО КУРЕНИЯ НЕ ДОСТИГАЕТСЯ ПОДАВЛЯЮЩИМ БОЛЬШИНСТВОМ РАБОТНИКОВ ЯДЕРНОЙ ИНДУСТРИИ ВСЕХ ПЕРИОДОВ ЗАНЯТОСТИ

To date, there are about 100 meta-analyses for lung cancer and circulatory (cardiovascular) diseases (CVD) as the effects of second hand smoking (SHS). The obtained risk values (Relative Risk – RR, odds ratio – OR, etc.) are in the range of 1.2–1.3, but there are no definitively accepted estimates yet, and many estimates were not made in recent years. Both SHS and work at nuclear industry enterprises have become stereotypes in everyday and scientific everyday consciousness, meaning something harmful in everyday and professional terms. The present study compared the mortality risks from all cancers, lung cancer, and CVD for SHS and nuclear workers (NW). At the first stage, an umbrella review (review of reviews; overview) and meta-analyses of meta-analyses (meta-meta-analyses) on the risks of mortality from these pathologies as effects of SHS were performed. Umbrella review and meta-meta-analysis are regarded as the highest level of evidence and, thus, the identified risks can be conditionally considered as ‘standard’. There were insufficient data available for all cancer mortality rates after SHS; Therefore, the results from the meta-analysis by Kim A.S. et al, 2018 were used., and meta-meta-analyses were performed for lung cancer and CVD mortality. The risk values were in the range of 1.22–1.24, which replicates previous findings. At the second stage, the risks identified for SHS were compared with the risks of mortality from the named pathologies for NW. The sample of publications for NW, extracted from the database maintained by the authors, included the most representative cohorts in relation to nuclear installations: with maximum doses, as well as combined cohorts (14–15 countries and INWORK – 3 countries). Based on published ERRs per 1 Gy for a given NW population, the radiation doses that NW would have to accumulate to approach the mortality risks from SHS were calculated. To achieve SHS risks for all three disease types, NWs were found to need to receive radiation doses ranging from 129–183 mSv to 1.07–6.0 Sv. There have been no cases in which the risk from SHS was equivalent to exposure to low-dose radiation (up to 100 mGy); more often, doses were localized in the range of about 300–800 mSv, up to 6 Sv. Analysis of published data on dose distributions for NW has demonstrated that such doses are received either by a relatively small or vanishingly small proportion of NW. Risks for 80–96 % of NWs from various countries, including activities since the 1940s, did not reach the harms of chronic exposure to SHS. It is concluded that the decades-long study of risks for NW, in particular ‘low doses’, does not seem adequate without taking into account the magnitude of even weak, but poorly controlled risks of everyday life, and the data obtained once again improves the image of employment in the field of nuclear energy.

Measurement of the neutron total cross section of 9Be at the Back-n white neutron source of CSNS* *Supported by the National Key Research and Development Plan (2016YFA0401603), the National Natural Science Foundation of China (11675155, 11790321) and Foundation of President of China Academy of Engineering Physics (YZJJLX2016003)

The neutron total cross section data of 9Be are essential in the nuclear structure model research of light nuclei and nuclear power installations. The neutron total cross section of 9Be in the 0.3 eV−120 MeV energy region has been measured using time-of-flight and transmission methods with the Neutron Total Cross Sectional Spectrometer (NTOX) based on the multi-cell fast fission chamber at the China Spallation Neutron Source (CSNS)-Back-n white neutron source (Back-n). The fission count-neutron energy distributions of 235U and 238U without samples and with Be samples with three thicknesses were measured in the double-bunch operation mode for a beam power of 100 kW. The Bayesian method was used to eliminate the influence of the double-bunch problem on neutron measurement in the energy region above 10 keV. The neutron total cross section of 9Be results was consistent with ENDF/B-VIII.0 evaluation library data in the 0.3 eV−20 MeV energy region. In the energy ranges of 0.3 eV to 10 keV and 0.01 to 20 MeV, the deviations between our results and the evaluation results of ENDF/B-VIII.0 were within 2.5% and 15%, respectively. In the resonance energy region, the measured resonance energies in our experiment were 0.63, 0.82, and 2.8 MeV, respectively. The results showed that the total cross section uncertainties of three Be samples were within 2.2% in the energy region below 1 MeV. The total cross section uncertainty of 30 mm Be from 235U was the smallest and less than 5% in the energy region of 0.3 eV−120 MeV. The results of this experiment can provide technical support for further data analysis and related nuclear data evaluation.