Review
Polymer Science
Muhd Afiq Hizami Abdullah, Raizal Saifulnaz Muhammad Rashid, Mugahed Amran, Farzad Hejazii, N. M. Azreen, Roman Fediuk, Yen Lei Voo, Nikolai Ivanovich Vatin, Mohd Idzat Idris
Summary: This article provides a comprehensive review on the subject of radiation shielding concrete (RSC), highlighting its potential and development as an advanced concrete product for nuclear energy applications. The composition, shielding characteristics, mechanical strength, and durability of RSC are discussed, along with avenues for future research. The article emphasizes the advantages and potential of RSC in shielding harmful radiation.
Article
Nuclear Science & Technology
Riccardo Martellucci, Daniele Torsello
Summary: This study investigates the potential use of biochar as a neutron shielding material in concrete and finds that it has comparable or better shielding performance than commonly used materials, making it an interesting and greener alternative.
NUCLEAR ENGINEERING AND TECHNOLOGY
(2022)
Article
Construction & Building Technology
Totsawat Daungwilailuk, Chadet Yenchai, Wisarute Rungjaroenkiti, Phoonsak Pheinsusom, Chinnapat Panwisawas, Withit Pansuk
Summary: The present study aims to analyze the performance of concrete containing local minerals, barite and cut steel bars, in protecting against gamma-ray and fast-neutron radiation. The results show that using barite as aggregates can increase the radiation shielding capability, as well as the strength and density of specimens. Additionally, using cut steel bars as an additive material significantly enhances the attenuation coefficients of gamma-rays and neutrons.
CONSTRUCTION AND BUILDING MATERIALS
(2022)
Article
Construction & Building Technology
Ali Oz, Baris Bayrak, Esra Kavaz, Gokhan Kaplan, Oguzhan Celebi, Haluk Gorkem Alcan, Abdulkadir Cueneyt Aydin
Summary: This study investigated the efficiency of geopolymers produced with short curing time and low curing temperature against gamma and neutron radiation. It was found that using quartz sand instead of river sand increased the compressive strength of the mixtures, and increasing the curing temperature and time improved the mechanical properties of the mixtures.
CONSTRUCTION AND BUILDING MATERIALS
(2022)
Article
Nuclear Science & Technology
Santhosh M. Malkapur, Shobha S. Ghodke, P. N. Sujatha, Yashoda Singh, K. S. Shivakumar, Meghanath Sen, Mattur C. Narasimhan, Abhishek Pulgur
Summary: In this study, waste plastics and byproducts from the iron industry were used to create a novel concrete mix for radiation shielding. The results showed that this concrete mix exhibited acceptable compressive strength and significantly enhanced shielding capabilities against both gamma and neutron radiations.
PROGRESS IN NUCLEAR ENERGY
(2021)
Article
Nuclear Science & Technology
Mohamed A. E. M. Ali, A. F. Tawfic, Mostafa A. Abdelgawad, Mohamed Wagih, A. Omar
Summary: Gamma and neutron radiation have negative impacts on human health and the environment due to nuclear accidents. Radiation shielding, using concrete as the main component, is necessary. This research investigates the mechanical properties of concrete mixtures with ilmenite or tourmaline aggregates. Results show that ilmenite concrete has reduced compressive and tensile strength, while tourmaline concrete has superior strength. Both ilmenite and tourmaline concrete effectively attenuate gamma and neutron emissions.
PROGRESS IN NUCLEAR ENERGY
(2023)
Article
Construction & Building Technology
P. Tamayo, C. Thomas, J. Rico, S. Perez, A. Mananes
Summary: This study examines the use of siderurgical aggregates in concrete design for radiation shielding, showing that concrete with siderurgical aggregates exhibits intermediate performance in linear attenuation coefficient and neutron transmission rate compared to limestone aggregate and magnetite concrete. The increase in cement content and water-to-cement ratio leads to a decrease in linear attenuation coefficient and neutron transmission rate, with water-to-cement ratio having no significant impact on neutron transmission rate.
CONSTRUCTION AND BUILDING MATERIALS
(2022)
Review
Construction & Building Technology
Fitrotun Aliyah, Imam Kambali, Angga Fajar Setiawan, Yasmin Md Radzi, Azhar Abdul Rahman
Summary: Steel slag is a byproduct of the steel industry that has been increasingly utilized as a natural aggregate replacement in shielding concrete production. Despite some drawbacks, the addition of steel slag to concrete has proven to enhance its performance as an ionizing radiation shield. This systematic review provides a comprehensive overview of the research efforts on steel slag utilization in shielding concrete, including the characterization of steel slag, mix design and mechanical properties of concrete, and analysis of radiation test findings. The review concludes that while steel slag concrete can improve compressive and tensile strength, it may reduce workability and its radiation shielding performance at high temperatures.
CONSTRUCTION AND BUILDING MATERIALS
(2023)
Article
Chemistry, Inorganic & Nuclear
D. Hajdu, E. Dian, K. Gmeling, E. Klinkby, C. P. Cooper-Jensen, J. Osan, P. Zagyvai
Summary: The study investigated the composition and trace element concentrations of three concrete types considered for use in the European Spallation Source (ESS) ERIC. Realistic input data were developed for these materials, containing parent elements of dominant radioisotopes, and validated against measured data from neutron irradiation experiments.
APPLIED RADIATION AND ISOTOPES
(2021)
Article
Physics, Multidisciplinary
Sertac Ozturk
Summary: The study shows that adding gadolinium to water can significantly improve the radiation shielding properties of gamma rays and neutrons. The addition of gadolinium increases the linear attenuation coefficient values of water by about 60% for gamma radiation, while the increment of neutron macroscopic cross-section is about 40%.
Article
Chemistry, Physical
Mannu Bardhan Paul, Anirban Dutta Ankan, Himadri Deb, M. Monjur Ahasan
Summary: In this research, a concrete bunker model was developed to investigate the depth-dose profiles for various concrete compositions. The shielding properties, such as relaxation lengths and half value layers, were deduced using Monte Carlo simulation. Serpentine (3.3), Ilmenite I-Ia (3.5), Limonite with Steel Punch LS-a (4.54) and (80%G4_C+20% Fe+10%B) Mix-1 (2.9) were found to be the most efficient materials for shielding fast neutrons.
RADIATION PHYSICS AND CHEMISTRY
(2023)
Article
Computer Science, Information Systems
Hongje Jang, Myungryul Choi, Taesueng Song, Sungwook Kim
Summary: This paper proposes a method for measuring the shielding effectiveness (SE) of concrete based on the MIL-STD-188-125-1 standard. By using small concrete blocks as specimens, the accuracy is optimized in the frequency range of 600 MHz to 1.5 GHz. Results show that the proposed method can be used to ensure that buildings constructed with the same concrete have the same SE.
Article
Chemistry, Physical
Marzieh Hassanpour, Mehdi Hassanpour, Mohammadreza Rezaie, Eysa Salajegheh, Mohammad Rashed Iqbal Faruque, Mayeen Uddin Khandaker, D. A. Bradley
Summary: Concrete is widely used as a radiation shielding material, and this study evaluates the effects of adding pistachio shell (PS) and date palm leaf (PL) as natural additives to improve neutron shielding properties. Numerical studies using MCNP code show that incorporating PS and PL additives in concrete can enhance shielding performance against fast and thermal neutrons.
RADIATION PHYSICS AND CHEMISTRY
(2022)
Article
Engineering, Electrical & Electronic
B. Alshahrani, Canel Eke, Z. A. Alrowaili, Ateyyah M. Al-Baradi, H. Alsaeedy, Chalermpon Mutuwong, B. T. Tonguc, M. S. Al-Buriahi
Summary: Tellurite glass systems, including newly developed glasses containing Sb2O3 and V2O5, were examined for their radiation shielding capabilities against gamma, neutron, and charged-particles radiations in the energy range of 0.1 to 10 MeV. The study utilized FLUKA simulation and a suitable theoretical model to assess the performance of the glass system, with variations in HVLs of the TSP glasses observed.
JOURNAL OF MATERIALS SCIENCE-MATERIALS IN ELECTRONICS
(2021)
Review
Construction & Building Technology
Tomasz Piotrowski
Summary: This research presents a complex method for evaluating the shielding efficiency of concretes and mortars used in biological shields against ionizing radiation, particularly against neutrons. The study showed that material modification by polymers, gadolinium, and boron compounds can significantly enhance thermal neutron absorption, which is important for designing tailored shielding concrete in the future.
CONSTRUCTION AND BUILDING MATERIALS
(2021)
Article
Nuclear Science & Technology
Kecheng Jiang, Jinzhao Yang, Xueli Zhao, Lei Chen, Fujun Gou, Songlin Liu
Summary: The blanket, as a key component of the fusion reactor, plays important roles in breeding tritium, shielding neutrons, and extracting thermal energy for electricity generation. Understanding the characteristics of gas-liquid two-phase flow and mass transfer is essential for optimizing the design of tritium extraction units in the blanket.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
Anna-Elina Pasi, Teemu Karkela, Fredrik Borjesson Sanden, Unto Tapper, Tuula Kajolinna, Christian Ekberg
Summary: This study investigates the gas-phase interactions between tellurium and organic material under severe nuclear accident conditions. The results show that there is interaction between tellurium aerosols and organic material, leading to an increase in the gaseous fraction and changes in XPS spectra. Although the exact species are not identified, these findings raise questions about the behavior of tellurium and its reactions with organic material in severe accident conditions.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
Ao Zhang, Qingye Li, Chaoyong Zong, Fuwen Liu, Tianhang Xue, Jian Xiao, Xueguan Song
Summary: In this study, a high-fidelity computational fluid dynamics model was established to investigate the flow characteristics of a novel balanced globe valve. The study found that the size of the throttle orifice and valve disc displacement have a significant impact on fluid force. The findings provide a basis for the design and dynamic control of globe valves, and also have potential value for energy utilization.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
Wenbo Li, Yunqing Bai, Shuai Zhang, Yang Li, Ming Jin, Chunjing Li
Summary: In this study, a 3D-CFD model based on the SUPERCAVNA facility was established to analyze thermal stratification in liquid-metal-cooled nuclear reactors. The results show that the SKE model is the most accurate in predicting temperature distribution, and further parametric studies were conducted.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
Song Jin, Di Jiang, Dongmei Wang, Shaojie Wang, Zhen Wang
Summary: This study presents the fragility evaluation of a nuclear containment structure subjected to earthquake and subsequent internal pressure sequence. Nonlinear finite element model and ground motion records are used to analyze the nonlinear response and fragility of the structure. Results show that the distribution of maximum strain and displacement of the structure under earthquake and subsequent pressure are significantly different, with displacement distribution related to ground motion intensity levels.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
Kazumasa Shimada, Tatsuya Sakurahara, Pegah Farshadmanesh, Seyed Reihani, Zahra Mohaghegh
Summary: This research improves the realism of Level 3 probabilistic risk assessment for nuclear power plants by modeling the evacuation behavior of residents and incorporating two advancements. The first advancement uses evacuation speed from a transportation simulation code as input to the Level 3 PRA code, enabling explicit incorporation of spatiotemporal evacuation processes. The second advancement incorporates the probability of seismic damage to roadway bridges into Level 3 PRA and calculates evacuation routes and speeds considering the impact of seismic damage.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
F. Mascari, A. Bersano, M. Massone, G. Agnello, O. Coindreau, S. Beck, L. Tiborcz, S. Paci, M. Angelucci, L. E. Herranz, R. Bocanegra, Y. Pontillon, M. Berdai, O. Cherednichenko, A. Iskra, M. Nudi, P. Groudev, P. Petrova, F. Kretzschmar, F. Gabrielli, Z. Kanglong, V. Vileiniskis, T. Kaliatka, J. Kalilainen, M. Malicki, D. Gumenyuk, Y. Vorobyov, O. Kotsuba, P. Dejardin, M. Di Giuli, R. Thomas, I. V. Ivanov, F. Giannetti, M. D'Onorio, G. Caruso, M. Salay, T. Sevon
Summary: The MUSA project aims to analyze uncertainties and sensitivities associated with severe accidents using a harmonized approach, particularly focusing on source term figures of merit. The project applied and tested uncertainty quantification methodologies using the PHEBUS FPT1 test. The study found that scripting for coupling SA codes and uncertainty tools can increase flexibility, and careful consideration should be given to selecting the input uncertain parameters.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
Ian Greenquist, Nathan Capps
Summary: The US nuclear energy industry is investigating strategies to increase reactor operating cycle to 24 months. Multiphysics simulations tools and methodologies are being developed to predict the effects of this change during transient events such as loss-of-coolant accidents (LOCAs).
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
Guangchun Zhang, Hu Zhang
Summary: In this study, a neutron transport code called TARS is introduced, which is based on the discrete-ordinates discontinuous finite element method. TARS provides accurate and efficient solutions to the neutron transport equation, addressing existing challenges in the field. The evaluation results demonstrate that TARS generates highly accurate solutions and achieves high parallel computation efficiency.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
J. R. Daniels, M. M. R. Williams, M. D. Eaton
Summary: This paper presents the development and verification of a collision probability (CP) code for neutron transport in slabs and cylinders. The CP code is particularly useful for modelling layered systems of aqueous and organic plutonium nitrate. The code provides a computationally inexpensive alternative to higher fidelity codes like MCNP. It is effective for slab geometries with at least 0.7 g cm-2 plutonium, but its approximation for heterogeneous cylinders can lead to overestimation of neutron leakage. Increasing the cylinder radius to 40.0 cm improves the accuracy for systems with at least 2.75 kg plutonium. However, the code's accuracy decreases when modelling cylindrical geometries with dished ends and low plutonium content.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
Alexander A. Ryzhkov, Georgy V. Tikhomirov, Mikhail Yu. Ternovykh
Summary: This paper analyzes the impact of nuclear data uncertainties on the safety of advanced reactors, with a specific focus on angular distribution uncertainties. Through sensitivity and uncertainty analysis, key parameters for MOX3600 are identified, and a comparison of different libraries' uncertainties on the eigenvalue is performed.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
Y. Fontenla, A. Vidal-Ferrandiz, A. Carreno, D. Ginestar, G. Verdu
Summary: FEMFFUSION is an open source code that solves the multigroup neutron transport equation using the diffusion and the SPN approximations. It uses the finite element method to handle various geometries and problem dimensions, and has been verified against the C5G7 benchmark.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
J. Tyler Gates, Pavel V. Tsvetkov
Summary: The Optical Fiber Based Gamma Thermometer utilizes optical fiber as a distributed temperature sensor to measure the temperature of a thermal mass undergoing gamma heating and calculate the gamma flux data. This technology shows promise in determining the local power density within a nuclear reactor core and provides an unparalleled level of precision in reactor power measurement.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
A. de Lara, A. Schubert, E. Shwageraus, P. Van Uffelen
Summary: This study presents a new methodology to derive the radial form factor in the TRANSURANUS burnup model using simulations. The proposed methodology can be applied to different types of reactors, including LWRs and HWRs, and is suitable for advanced technology fuels.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
A. Bousbia Salah, M. Di Giuli, P. Foucaud, R. Iglesias, A. Malkhasyan, M. Salmaoui, L. E. Herranz
Summary: In the framework of the R2CA project, the application of advanced codes for evaluating radiological release under design basis accidents was considered. The study focused on a specific scenario and assessed the results obtained by different organizations using different computational tools and approaches. The outcomes highlighted modeling differences and challenges in carrying out such analysis.
ANNALS OF NUCLEAR ENERGY
(2024)
