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Lightweight Heat Pipe Radiator for Nuclear Reactor Power Systems on Lunar Surface Nucl. Technol. (IF 1.5) Pub Date : 2024-04-19 Mohamed S. El-Genk, Timothy M. Schriener
Heat rejection radiators of nuclear reactor power systems for space exploration and for planetary surface power are the largest component by volume and mass, depending on the radiator’s design and ...
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Evaluating Material Attractiveness of Minor Actinide Nuclear Fuel Intended for a Waste Transmutation Lead-Cooled Fast Reactor Nucl. Technol. (IF 1.5) Pub Date : 2024-04-19 Débora M. Trombetta, Erik Branger, Markus Preston, Sophie Grape
Long-lived high-level waste from commercial nuclear power reactors is a problem that concerns stakeholders and scientists working in the back end of the nuclear fuel cycle. Nuclear waste transmutat...
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Surrogate Model of Solved Poisson Kriging Method for Radiation Field Reconstruction Nucl. Technol. (IF 1.5) Pub Date : 2024-04-19 Zhenyu Wang, Zungang Wang, Jian Sun, Zhiyuan Li, Shanxue Xi, Xing Wei, Weiqi Huang, Chunzhi Zhou
Reverse reconstruction methods for the radiation field do not require information on the radioactive source and are capable of constructing the radiation field using a small amount of monitoring da...
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Theoretical Calculation of Gamma-Ray and Neutron Shielding Properties for CsPbBr3-Polypropylene Composite Material Nucl. Technol. (IF 1.5) Pub Date : 2024-04-17 Junfeng Zhao, Yuanjie Sun, Yue Zhang, Zhigang Li, Hongtao Zhao, Qingyu Wang
The impact of CsPbBr3, known for its high atomic number and cross section with neutrons, on the gamma-ray and neutron shielding properties of CsPbBr3-polypropylene (PP) composite material was inves...
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Review of Filtered Containment Venting System (FCVS) Eleven Years After Fukushima Accident Nucl. Technol. (IF 1.5) Pub Date : 2024-04-17 Jawaria Ahad, Amjad Farooq, Masroor Ahmad, Naseem Irfan, Khalid Waheed
Severe accidents in nuclear power plants can breach the integrity of containment due to pressure build up, resulting in the release of radioactive products. Special interest has been shown towards ...
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Turbulent Particle Flow in Spent Nuclear Fuel Storage Systems Nucl. Technol. (IF 1.5) Pub Date : 2024-04-15 Sarah R. Suffield, William A. Perkins, Ben J. Jensen, Brady D. Hanson, Steven B. Ross
Deposition models are being developed with the commercial computational fluid dynamics software STAR-CCM+ to evaluate particulate deposition on spent nuclear fuel (SNF) canisters. The primary parti...
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Neutronic Analysis of the Conceptual Molten Uranium Breeder Reactor Using MCNP and SCALE Tools Nucl. Technol. (IF 1.5) Pub Date : 2024-04-15 Zeyun Wu, Christian Pochron, Mihai (Mike) G. M. Pop, Neal Mann
The Molten Uranium Breeder Reactor (MUBR) is a radically new reactor concept with a mixed-energy spectrum. MUBR is fueled with molten uranium metal in large-diameter fuel tubes and is cooled by cir...
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Fault Detection and Isolation in Simulated Batch Operation of Fine Motion Control Rod Drives Nucl. Technol. (IF 1.5) Pub Date : 2024-04-15 Ark O. Ifeanyi, Daniel Dos Santos, Abhinav Saxena, Jamie Coble
Control rods and elements manage the power distribution in nuclear reactors through the motion of banks of rods distributed throughout the core. These positional changes are achieved through the ac...
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Fluid-Solid Interaction Analysis at the Slip Joint of a Boiling Water Reactor Type 5 Jet Pump Nucl. Technol. (IF 1.5) Pub Date : 2024-04-15 J. Cruz-Castro, L. H. Hernández-Gómez, Y. López-Grijalba, E. Hernández-Palafox, J. A. Beltrán-Fernández, J. I. E. Palacios-Hernández, I. A. Alarcón-Sánchez
In this paper, the fluid-solid interaction of a jet pump of a boiling water reactor type 5 (BWR/5), with its riser subjected to a leakage flow through its slip joint, is reported. This is a fluid-e...
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Extrapolation of Monte Carlo–Derived Noble Gas Air-Submersion Effective Dose Rate Coefficients for Selected Occupational Settings to Other Geometries and Radionuclides Nucl. Technol. (IF 1.5) Pub Date : 2024-04-15 John N. Hamawi, Pedro B. Pérez
External exposures to airborne radioactivity at nuclear power sites are typically based on semi-infinite clouds with uniform concentrations and corresponding effective dose rate coefficients (EDRCs...
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Adsorption of Radioactive Iodine Using Nanocarbon on ETS-10 as Adsorbent Nucl. Technol. (IF 1.5) Pub Date : 2024-04-12 Chaithanya Balumuru, Krishnan Raja, Piyush Sabharwall, Vivek Utgikar
Laboratory-synthesized nanocarbon pelletized with titanosilicate (ETS-10) as a support matrix has been investigated for the capture of radioactive iodine present as methyl iodide (CH3I) in the off-...
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Calculation and Discussion for Crack Driving Force of Dissimilar Metal Welded Joint of Nuclear Power Equipment Nozzle and Safe End Nucl. Technol. (IF 1.5) Pub Date : 2024-04-12 Dasheng Wang, Jin Ting, Xu Xiao, Tan Jianping, Zhang Kun, Wang Guozhen
This study investigates the effects of the material mechanical properties heterogeneity and strength mismatch variation on crack driving forces for cracks in a dissimilar metal welded joint (DMW) o...
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Combustion Properties of Glove-Box Panel Resins Under Fire Accidents Nucl. Technol. (IF 1.5) Pub Date : 2024-04-12 Shinsuke Tashiro, Gunzo Uchiyama, Takuya Ohno, Yuki Amano, Ryoichiro Yoshida, Koji Watanabe, Hitoshi Abe, Yuichi Yamane
Contributing to the confinement safety evaluation of glove boxes (GBs) connected to high-efficiency particle air filters for radioactive materials under fire accidents, combustion tests of a flamma...
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Two-Fluid and Discrete Population Balance Model for Simulation of Batch Sedimentation Relevant to Plutonium Reconversion Nucl. Technol. (IF 1.5) Pub Date : 2024-04-12 Saroj Kumar Panda, Panantharayil Vishnu Anand, Vivek Kumar Mishra, Ramachandran Pillai Rajeev, Konda Athmaram Venkatesan, Krishnamurthy Ananthasivan
There are widespread occurrence and application of solid-liquid sedimentation processes among different industries. Therefore, it becomes important to understand the hydrodynamic inside the process...
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Exploring the Feasibility of Kuiper Belt Missions Supported by Centrifugal Nuclear Thermal Propulsion Nucl. Technol. (IF 1.5) Pub Date : 2024-04-12 William Ziehm, L. Dale Thomas
Missions to the Kuiper belt have previously been carried out only as flybys and with very small payloads. Investigating launch windows for Kuiper belt missions supported by centrifugal nuclear ther...
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Development of a New Correlation for Saturated Flow Boiling Heat Transfer in a Helically Coiled Tube Nucl. Technol. (IF 1.5) Pub Date : 2024-04-12 Min Gi Kim, Byongjo Yun, Jae Jun Jeong
We have developed a heat transfer correlation for saturated flow boiling of water in a helically coiled tube. Initially, we collected experimental data encompassing a broad spectrum of thermal-hydr...
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Progress in Fast Modular Reactor Conceptual Design Nucl. Technol. (IF 1.5) Pub Date : 2024-04-11 Hangbok Choi, John Bolin, Oscar Gutierrez, Radu Curiac, Mohammad Alavi, Matthew Virgen, Ed Chin, James Beaver, Pascal Brocheny, Geoffrey Beausoleil, Abdellatif M. Yacout, Sal Rodriguez, Michael Corradini, Daejong Kim, Steven L. Krahn, Eric Thornsbury
The Fast Modular Reactor (FMR) is a 100-MW(thermal) gas-cooled fast reactor being developed by General Atomics Electromagnetic System with the goal of developing a FMR for flexible and dispatchable...
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Novel Approach for Network Data Exchange Among Safety-Related Control Systems of Nuclear Reactors Nucl. Technol. (IF 1.5) Pub Date : 2024-04-11 Aditya Gour, R. P. Behera, Tom Mathews
Industrially mature digital networking technologies form the backbone of the distributed control architectures of nuclear reactors. Typically, hundreds of control systems responsible for assuring s...
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Development of Obligation Tracking System for Internationally Controlled Items in Accordance with Bilateral Nuclear Cooperation Agreements Nucl. Technol. (IF 1.5) Pub Date : 2024-04-11 Mun-Young Ryu, Hyun-Jo Kim, Jin-Ha Choi
A Bilateral Nuclear Cooperation Agreement serves as a means to promote effective and universal cooperation while simultaneously guaranteeing overall nuclear nonproliferation. This agreement is lega...
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Mixing of Hydrogen-Steam Buoyancy Jets Released into the Upper Atmosphere of the Containment Building Nucl. Technol. (IF 1.5) Pub Date : 2024-04-11 Youngsu Na
This study evaluates the spatial dilution of hydrogen concentration caused by steam-hydrogen buoyancy jets rising through the open top of the steam generator compartment during a loss-of-coolant ac...
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A Study on Boiling Heat Transfer Performance of TiO2-CNTs Hybrid Nanofluid on a Downward-Facing Heating Surface Nucl. Technol. (IF 1.5) Pub Date : 2024-04-11 Songling Liu, Huai-En Hsieh, Shiqi Wang
In-vessel retention through external reactor vessel cooling (IVR-ERVC) is a strategy used to respond to nuclear reactor accidents. One of the key performance indicators determining its feasibility ...
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Creep Fatigue Analysis of the 316SS Monolith in the MegaPower Heat Pipe Reactor Nucl. Technol. (IF 1.5) Pub Date : 2024-04-11 Yong Wang, Lichuang Liang, Jun Tian, Dongchuan Su, Hui Li, Naibin Jiang
The heat pipe reactor represents a promising high-temperature microreactor design comprising heat pipes, fuel rods, and monoliths. Prolonged operation at elevated temperatures leads to an obvious t...
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Modified Evaporation Model for ATHLET System Code in a Passive Containment Cooling System for Nuclear Safety Nucl. Technol. (IF 1.5) Pub Date : 2024-04-08 Michel Haag, Iurii Dolganov, Stephan Leyer
The presented work deals with the improvement of the evaporation model of the ATHLET (Analysis of Thermal and Hydraulics of Leaks and Transients) system code to be applied to a passive containment ...
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Delayed Heating Calculations Using the MCNP-ORIGEN Activation Automation Tool Nucl. Technol. (IF 1.5) Pub Date : 2024-04-08 Roberto E. Fairhurst-Agosta, Tomasz Kozlowski
An accurate assessment of the deposited energy across a reactor geometry allows for a better determination of the heat removal requirements and ensures effective cooling after shutdown. This work d...
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A Blowdown Critical Heat Flux Experimental Vehicle Nucl. Technol. (IF 1.5) Pub Date : 2024-04-08 Musa Moussaoui, Wade Marcum
In the most challenging nuclear power plant accidents, transient critical heat flux (CHF) is a primary phenomenon that drives peak cladding temperature, and ultimately, fuel failure. It has not yet...
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PCMI Uncertainty and Sensitivity Analysis of Es-Salam Reactor Fuel Rods During Steady-State Operations Nucl. Technol. (IF 1.5) Pub Date : 2024-04-05 Djillali Saad, Mohamed Elhadi Boulheouchat, Mohamed Bouaouina, Tahar Zidi
Nuclear safety relies heavily on the quality of the results of numerical simulation codes. Among the various components of the simulation of the installation are the pellet-cladding mechanical inte...
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Evaluation of Reaction Rate Distribution for Shielding Region in the Prototype Fast Reactor Monju Nucl. Technol. (IF 1.5) Pub Date : 2024-04-05 Tetsuya Mouri, Taira Hazama, Hiroki Katagiri, Kazuya Ohgama
The reliability and usefulness of the reaction rate distribution data measured in the prototype fast breeder reactor Monju were examined through a comparison with a calculation using JENDL-4.0, mai...
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Reconstruction of γ Dose Rate Field and Algorithm Validation Based on Inverse Distance Weight Interpolation Nucl. Technol. (IF 1.5) Pub Date : 2024-04-03 Biao Zhang, Jinjia Cao, Shuang Lin, Yingming Song
The inverse distance weighting (IDW) interpolation algorithm is used to reconstruct the γ radiation field. The traditional IDW interpolation algorithm is improved. The power exponent of distance P ...
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Effect of Cooling Pump Transient Power Supply on ETRR-2 Safety Parameters Nucl. Technol. (IF 1.5) Pub Date : 2024-04-04 Abdelfatah Abdelmaksoud, Asmaa Gamal, Ahmed R. Adly
The primary goals of the engineering design for nuclear reactors involve safeguarding the integrity of the reactor core. Preserving the integrity of the cladding material is especially crucial, as ...
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Optimization of Elliptical U-tube Heat Exchanger (EUTHE) for Spray Cooling Based on the Taguchi and CFD Method Nucl. Technol. (IF 1.5) Pub Date : 2024-04-02 Binqi Hao, He Zhou, Xiaofeng Li, Zu’An Wang, Shunyang Li, Pengfei Wang
The elliptical U-tube heat exchanger (EUTHE) is widely used in various cooling systems of nuclear engineering for its simple geometrical structure and small space cost. In this paper, a two-phase f...
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Enhancement of Gamma-Ray and Neutron Shielding Properties of TeO2-Li2O-ZnO-Nb2O5 Glass System with the Addition of Sm2O3 Nucl. Technol. (IF 1.5) Pub Date : 2024-04-02 Zhigang Li, Junfeng Zhao, Yuanjie Sun, Yi Wang, Hongtao Zhao
Radiation shielding glass is widely used, as it protects people from ionizing radiation while allowing for the observation of irradiated areas. However, the performance of even the best-performing ...
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A Semi-Analytical Prediction Model for Fluid-Elastic Instability of a Normal Triangular Tube Array Under Transverse Flow Excitation Nucl. Technol. (IF 1.5) Pub Date : 2024-04-02 Gongbo Chen, Naibin Jiang
The heat exchange tubes in the steam generator are susceptible to vibration caused by fluid flow, which can lead to damage to both the tubes and their support structures due to collisions. To enhan...
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Drying and Analysis of Aluminum (Oxy)hydroxide Films for Dry Storage of Aluminum-Clad Spent Nuclear Fuels Nucl. Technol. (IF 1.5) Pub Date : 2024-04-01 Robert J. Demuth, Anna L. D’Entremont, Rebecca Smith, Robert L. Sindelar, Travis W. Knight
In aluminum-clad spent nuclear fuels, an (oxy)hydroxide layer on the surface of the cladding hosts chemisorbed water formed during reactor and post-discharge exposure to water. Any residual water i...
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Determination of Gain Scheduling Parameters for Loss of a Feedwater Pump Transient Mitigation Using Neural Networks Nucl. Technol. (IF 1.5) Pub Date : 2024-04-01 Ryan J. Hoover, Kenji Shimada
Transient mitigation for nuclear power plants is essential for safe operation. The fourth industrial revolution brings with it the potential for data-based predictive maintenance and identifying re...
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Best Estimate Plus Uncertainty Analysis of Station Blackout Transient in Pool-Type Research Reactor Nucl. Technol. (IF 1.5) Pub Date : 2024-04-01 Amitanshu Mishra, Paban Kumar Guchhait, Samiran Sengupta
Simulation of a station blackout (SBO) scenario was carried out for an open pool–type nuclear research reactor. The SBO transient was analyzed using the best estimate (BE) thermal-hydraulic code RE...
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Estimation of Densities of Aqueous Actinide Solutions Ranging from Pure Water to Hydrated Crystals Nucl. Technol. (IF 1.5) Pub Date : 2024-03-27 Shekhar Kumar
The density of aqueous solutions containing actinide nitrates is an important parameter for process design, equipment design, and remote operation/control. It is also significantly important for th...
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Numerical Analysis of Effects of Vane Deflection Angle on Flow-Thermal Characteristics in a Fuel Rod Assembly Nucl. Technol. (IF 1.5) Pub Date : 2024-03-25 Satish Kumar Dhurandhar, S. L. Sinha, Shashi Kant Verma
The utilization of a grid spacer with vane is a significant component within reactor fuel channels. The presence of the vane has a notable impact on the mixing of flow and the enhancement of heat t...
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Mobile Application Development Plan for Fire Influence Analysis Using Algebraic Models Nucl. Technol. (IF 1.5) Pub Date : 2024-03-25 Yongjae Kim, Seokhyeon Han, Seungjun Oh, Samwon Chung
There are numerous computational programs available for fire influence analysis; however, currently, there is no computational program in Korea specifically designed to aid Authority Having Jurisdi...
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Simulation of Neutron Leakage Variations at Fuel Substitution in a Small Modular Reactor and Implications for Unattended Safeguards Monitoring Nucl. Technol. (IF 1.5) Pub Date : 2024-03-26 Markus Preston, Erik Branger, Sophie Grape, Olena Khotiaintseva
According to a recently proposed nuclear safeguards technique, monitoring the power-normalized, ex-core neutron detection rate over time could be used to detect undeclared changes to the fissile co...
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Model Development for Thermal-Hydrology Simulations of a Full-Scale Heater Experiment in Opalinus Clay Nucl. Technol. (IF 1.5) Pub Date : 2024-03-26 Teklu Hadgu, Edward Matteo, Thomas Dewers
Disposal of commercial spent nuclear fuel in a geologic repository is studied. In situ heater experiments in underground research laboratories provide a realistic representation of subsurface behav...
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Experimental Model to Study Characteristics of Radon Cover in Waste Landfills Nucl. Technol. (IF 1.5) Pub Date : 2024-03-25 Nora Nassiri-Mofakham, Mojtaba Kakaei
Waste from resource extraction industries contains uranium and thorium decay chain radionuclides. One important radiological impact of these wastes is the release of radon into the atmosphere. Ther...
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Development of Two-Step Method for Fast Chloride MSR Neutronics Nucl. Technol. (IF 1.5) Pub Date : 2024-03-21 Kyra Lawson, Nicholas R. Brown
This work presents neutronics models of a small and large fast-spectrum molten chloride-salt reactor. The models are similar to designs being pursued by industry, and they may serve as generic prec...
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Effects of Impurities and Additives on Interactions of Nuclear-Grade Graphite with Molten LiF-NaF-KF Nucl. Technol. (IF 1.5) Pub Date : 2024-03-21 Krishna Moorthi Sankar, Preet M. Singh
It has been widely acknowledged that the presence of impurities in molten fluoride salt can alter the salt/material interactions. However, the effects of various impurities such as oxides, metal fl...
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Release Behavior of Gaseous Ruthenium Tetroxide During Heating of High-Level Liquid Waste Simulant During Simulated Accident Conditions Nucl. Technol. (IF 1.5) Pub Date : 2024-03-21 Naoki Yoshida, Takuya Ohno, Yuki Amano, Ryoichiro Yoshida, Hitoshi Abe, Yuichi Yamane
A malfunction of the cooling system of high-level liquid waste (HLLW) and the failure of countermeasures may lead to the evaporation to dryness due to the loss of cooling functions (EDLCF) of the H...
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Density Equation for Mixed Organic Solutions Containing tri-n-butyl Nitrate, n-Dodecane, Nitric Acid, and Nitrates of Heavy Metals Nucl. Technol. (IF 1.5) Pub Date : 2024-03-21 Shekhar Kumar
Several empirical equations were available in the literature for density equation for tri-n-butyl phosphate (TBP)–bearing mixed organic solutions used in the PUREX/UREX process; however, all most a...
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A Novel Communication Framework for Reduction of Staffs in Advanced MCRs of SMRs: A Prototype Development of a NLP-Based System Nucl. Technol. (IF 1.5) Pub Date : 2024-03-21 Taejin Kim, Donghan Yoo, Jongin Yang, Seoryong Koo, KyungTae Lim
As small modular reactors are gaining attention as the future of nuclear energy, it has become increasingly imperative to minimize the number of required operators in order to improve economic comp...
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Polarization of Compton-Scattered Prompt Gamma-Ray Technique for HEU Detection at 186 keV Nucl. Technol. (IF 1.5) Pub Date : 2024-03-19 Athanas Mutiso, Ayodeji B. Alajo, Xin Liu
Prompt gamma-ray polarization is a practical method for detecting highly enriched uranium (HEU) in concealed sources. It also provides information on their geometry, magnetic fields, and radiation ...
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Numerical Simulation on Dispersion of Hydrogen Leaked in Particle Layers of Glass Beads and Soil Nucl. Technol. (IF 1.5) Pub Date : 2024-03-18 Atsuhiko Terada, Ryuji Nagaishi
In order to understand the dispersion of hydrogen (H2) leaked in packed beds of nonporous/porous particles in a partially open space practically, the dispersion of H2 in the particle layers of glas...
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Prediction of Flooding Characteristic in Pulsed Disc and Doughnut Extraction Column Using LASSO Method Nucl. Technol. (IF 1.5) Pub Date : 2024-03-14 Lei Jin, Hui He, Yu Zhou, Hongguo Hou, Meng Zhang, Yang Gao
For achieving high separation efficiency and a large throughput in the nuclear fuel reprocessing industry, it is crucial to have a profound understanding of the flooding characteristics in pulsed d...
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Characterization of a Fast Neutron Irradiation Facility Using a Stilbene Scintillation Detector Nucl. Technol. (IF 1.5) Pub Date : 2024-03-15 Felix Pino, Jessica C. Delgado, Matteo Polo, Erica Fanchini, Anna Selva, Joana Minga, Gianmarco Torilla, Lodovico Ratti, Sandra Moretto
This paper describes the characterization of a fast neutron facility located at Legnaro National Laboratories’ Van de Graaff CN accelerator. The neutron flux is produced by the 9Be(p,xn) reactions...
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Discrete Element Method Simulation of the Idaho Calcine Simulant for Hot Isostatic Pressing Canister-Filling Process: Part 1 Nucl. Technol. (IF 1.5) Pub Date : 2024-03-13 Simon Chung, Martin Stewart, Andrew Grima, Peter Wypych, Sam Moricca
In preliminary engineering studies and equipment commissioning, readily available simulants with certain resemblances to the target waste, such as particle size, may be employed. However, for the v...
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Elastic, Anelastic, and Thermal Properties of P91 Steel with Microstructural Variability Nucl. Technol. (IF 1.5) Pub Date : 2024-03-13 Z. Miles, A. Balodini, T. Seuaciuc-Osorio, J. J. Wall, M. Guimaraes, A. Zevalkink, S. K. Chakrapani
Grade 91 steel has been used in nuclear and fossil power plants since the 1970s. Manufacturing variabilities resulting from manufacturing, repair, and management activities have been attributed to ...
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Thermal and Electrical Performance Analyses of a 100-W Radioisotope Thermoelectric Generator for Space Exploration Nucl. Technol. (IF 1.5) Pub Date : 2024-03-11 Shiping Wei, Jin Wang, Zhixin Ma, Ming Jin, Chunjing Li, Yuan Hu
A 100-W radioisotope thermoelectric generator (RTG) is by far the most suitable power supply for long-term deep space exploration where solar power would not be feasible. Understanding the thermal ...
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Temperature-Dependent Swelling in Helium Ion Irradiated Vanadium Nucl. Technol. (IF 1.5) Pub Date : 2024-03-11 Weiping Zhang, Yiheng Chen, Wenrui Cheng, Liping Guo, FengFeng Luo
Vanadium is a typical low-activation metal and has the advantages of lower neutron irradiation activation, better mechanical properties at high temperature, and higher compatibility with the liquid...
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Simulation of Readout Electronics for Nuclear Radiation Detector Using MATLAB Program Nucl. Technol. (IF 1.5) Pub Date : 2024-03-11 Jamal-Eddin Assaf, Zuheir Ahmad
A computer program was developed using the MATLAB programming language to simulate the electronics readout for a radiation detector system. The function of each stage of this system is described by...
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Methodology to Assist in Training Maneuvers of Operation of Pumps of a Nuclear Plant Using Virtual Reality Nucl. Technol. (IF 1.5) Pub Date : 2024-03-11 Daniel Mól Machado, Gustavo Souza Pinheiro dos Santos, Andre Cotelli do Espirito Santo, Antonio Carlos de Abreu Mól, Celso Marcelo Franklin Lapa, Claudio Henrique dos Santos Grecco
In power plants, one of the important maneuvers is the switching of pumps, where incorrect execution can even cause the unit to shut down. Therefore, the objective of this paper is to create a virt...
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Evaluation of Reaction Rate Distribution Measurement in the Prototype Fast Reactor Monju Nucl. Technol. (IF 1.5) Pub Date : 2024-03-11 Kazuya Ohgama, Taira Hazama, Hiroki Katagiri, Atsushi Takegoshi, Tetsuya Mouri
In the prototype fast breeder reactor Monju, reaction rate distributions of the fission reaction rates of 239Pu, 235U, and 238U and the capture reaction rate of 238U were measured using activation ...
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Multiphysics Analysis of PLOFC and DLOFC Accidents in the HTGR-TR Nucl. Technol. (IF 1.5) Pub Date : 2024-03-11 Annie Berens, Nicholas Meehan, Mason Fox, Isabelle Lindsay, Nicholas R. Brown
High-temperature, gas-cooled reactors (HTGRs) are promising advanced reactor designs. Leveraging passive safety features, higher core outlet temperatures, previous commercial operational experience...
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Foreword: Special issue on Heavy Liquid Metal–Cooled Fast Reactor Technology Nucl. Technol. (IF 1.5) Pub Date : 2024-03-08 Mariano Tarantino, Giacomo Grasso, Pierdomenico Lorusso, Kamil Tuček
Published in Nuclear Technology (Vol. 210, No. 4, 2024)
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Measurement of Aerosol Transmission Through a Stress Corrosion Crack–Like Geometry Nucl. Technol. (IF 1.5) Pub Date : 2024-03-07 Samuel Durbin, Ramon Pulido, Philip Jones, Adrian Perales
The formation of a stress corrosion crack (SCC) in the canister wall of a dry cask storage system (DCSS) has been identified as a potential issue for the long-term storage of spent nuclear fuel. Th...