-
OpenMC Interpretation of FNS SINBAD Shielding Benchmark Experiments Fusion Sci. Technol. (IF 0.9) Pub Date : 2024-03-25 Bamidele Ebiwonjumi, Stefano Segantin, Ethan Peterson
The Fusion Neutron Source (FNS) clean benchmark experiments on tungsten, vanadium, and beryllium assemblies from the SINBAD (Shielding Integral Benchmark Archive and Database) are analyzed to exper...
-
Accuracy Compensation Based on Optimized Neural Network for a Robotic Patient Positioning System with 6 Degrees of Freedom Used in Proton Therapy System Fusion Sci. Technol. (IF 0.9) Pub Date : 2024-03-18 Jianghua Wei, Yuntao Song, Kaizhong Ding, Yonghua Chen, Hui Yuan, Zhoushun Guo
Proton therapy for tumor treatment is a typical application of nuclear technology. For proton therapy systems, robotic patient positioning systems (PPSs) are increasingly used because of their high...
-
Recent Upgrade of the Magnetic Diagnostic System in the Alvand-U Tokamak Fusion Sci. Technol. (IF 0.9) Pub Date : 2024-03-05 Yahya Sadeghi, Hossain Rasouli, Farid Sedighi, Mehdi Jafargholi, Samaneh Yarmahmoodi, Hojjat Babaee
The main acting parameters in tokamak plasma experiments, such as currents and electric and magnetic fields, are present inside and outside the plasma volume. To analyze the changes in the shape of...
-
Determination of the Surface-Rate Coefficients of Deuterium Through Nickel by Gas-Driven Permeation Experiments in Surface-Limited Regime Fusion Sci. Technol. (IF 0.9) Pub Date : 2024-02-29 Nicolae Bidica, Narcisa Ghimis, Bogdan Monea
Tritium permeation through structural materials of fusion reactors is an important issue from both safety and tritium self-sufficiency points of view. Mutual influences among hydrogen isotopes are ...
-
Detritiation of the Organic Material in the MSO Process Fusion Sci. Technol. (IF 0.9) Pub Date : 2024-02-27 Vojtěch Galek, Anna Sears, Petr Pražák, Lucie Karásková-Nenadálová
Tritium is a radioactive isotope of hydrogen, and due to its limited supply and related high price, it is necessary to recover it from tritiated materials via detritiation technologies. The number ...
-
Optical System Design for Laser-Induced Fluorescence Study of Helium Atoms on the Linear Plasma Device Fusion Sci. Technol. (IF 0.9) Pub Date : 2024-02-26 Bo Shi, Chenyao Jin, Chi-Shung Yip, Di Jiang, Wei Zhang, Wei Lu, Wenjing Pu, Junli Qi, Huihui Shan, Changjiang Zhang
According to the characteristic spectral lines of helium atoms, an optical system for the laser-induced fluorescence study of helium atoms has been designed. The design includes a helium spectral s...
-
Axial Concentration of Dissolved Deuterium by Dispersion in a LiPb Experimental Loop Fusion Sci. Technol. (IF 0.9) Pub Date : 2024-02-12 Fumito Okino, Yukinori Hamaji, Teruya Tanaka, Juro Yagi
The axial concentration of deuterium by dispersion in a circulating liquid lithium-lead (LiPb) loop was analyzed and experimentally verified. In previous fusion blanket studies, the tritium transpo...
-
Measurement of Hydrogen Permeation Fluxes Through Tungsten Deposition Layer Growing by Hydrogen Plasma Sputtering and Observation of Microstructure Fusion Sci. Technol. (IF 0.9) Pub Date : 2024-01-31 Kentaro Masuta, Yuki Hara, Makoto Oya, Naoaki Yoshida, Kazunari Katayama
Hydrogen isotope behavior, especially permeation and retention, at the first wall is important for the safety and fuel sufficiency of fusion reactors. This study focuses on the deposition layer for...
-
A Critical Review of Fabrication Strategies, Separation Techniques, Challenges, and Future Prospects for the Hydrogen Separation Membrane Fusion Sci. Technol. (IF 0.9) Pub Date : 2024-01-22 Vamsi Krishna Kudapa, Paramjeet Singh Paliyal, Arnab Mondal, Surajit Mondal
Fossil fuels provide over 80% of the world’s current energy demand, which results in the release of large amounts of greenhouse gases (GHGs). In contrast to the emissions of GHGs caused by the comb...
-
Facile Synthesis of Stable Nanosized Silver Clusters in Plasma Discharge Under Ultrasonic Cavitation Fusion Sci. Technol. (IF 0.9) Pub Date : 2024-01-17 N. A. Bulychev
This work is devoted to the study of plasma-chemical processes determined by the combination of the effect of thermally nonequilibrium, low-temperature plasma and intensive ultrasonic vibrations in...
-
Application of Adaptive Channeling of Low-Energy Particles in Above-Target Graphene Film to Optimize Accelerator Nuclear Fusion in Unstructured Targets Fusion Sci. Technol. (IF 0.9) Pub Date : 2024-01-17 V. I. Vysotskii, M. V. Vysotskyy, S. Bartalucci
A method for optimizing controlled nuclear fusion in an unstructured target using low-energy particles (e.g., hydrogen) is discussed. The main idea of the method is the use of quasi channeling of s...
-
Tritium Content in Komatsuna Cultivated in Tritium-Contaminated Peat Soil Fusion Sci. Technol. (IF 0.9) Pub Date : 2024-01-17 Portuphy Michael Ofotsu, Kazunari Katayama, Takahiro Matano
Tritiated water from fusion power reactors will be the next major issue when fusion technology comes fully onstream. Effective radiation protection measures will be implemented when the scope of it...
-
Richtmyer on Shocks “Proposed Numerical Method for Calculation of Shocks,” an Annotation of LA-671 Fusion Sci. Technol. (IF 0.9) Pub Date : 2024-01-11 L. G. Margolin, K. L. van Buren
Here we reproduce the complete text of Los Alamos Scientific Laboratory Report LA-671 authored by Robert Richtmyer in 1948. This report, though unpublished, is arguably one of the most important an...
-
Density Functional Theory Investigation of Cu, Ni, and Ag Inclusion in ZSM-5 to Study Dihydrogen Binding for Cryogenic Molecular Sieve Bed Adsorber in Nuclear Fusion Systems Fusion Sci. Technol. (IF 0.9) Pub Date : 2024-01-12 V. Gayathri Devi, Kannan Aravamudan, Amit Sircar
A computational investigation of Cu-, Ni-, and Ag-introduced ZSM-5 as potential hydrogen storage materials for nuclear fusion energy systems is performed. Among the 24 distinct tetrahedral sites of...
-
Analysis of the Mechanism of Microwave Radiation Generated by the Weak Interaction Between Relativistic Electron Beam and Plasma with a Transverse Magnetic Field Fusion Sci. Technol. (IF 0.9) Pub Date : 2024-01-11 Shen Gao, Jin-Ke Zhang, Xin-Ting Tang, Kang Chen
This article establishes a physical model of the interaction between a surface electron beam and the plasma with a transverse magnetic field. The dispersion relation of the beam-plasma interaction ...
-
Numerical Calculations of Liquid-Metal Magnetohydrodynamic Flows in Rectangular Ducts with Sudden Expansions Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-12-20 Hiroshige Kumamaru
Relating to the design of liquid-metal blankets in a fusion reactor, numerical calculations have been performed on liquid-metal magnetohydrodynamic (MHD) flows in rectangular ducts with sudden expa...
-
Instrumentation and Control for Tritium Compatible Hydrogen Generator Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-12-19 Ovidiu Balteanu, Iuliana Stefan, Ciprian Bucur, George Ana
Hydrogen generators that use a proton exchange membrane (PEM) cell stack for water electrolysis have various applications, one of them being combined electrolysis catalytic exchange installations. ...
-
Preliminary Design of a Cryogenic System with GM Cryocooler for Testing the Hydrogen Condensers of the Distillation Columns Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-12-14 Catalin Brill, Sebastian Brad, Claudia Bogdan, Aleksandr Grafov, Oleksandr Sirosh, Alin Lazar, Mihai Vijulie, Viorel Badescu
The Experimental Pilot Plant for Tritium and Duterium Separation has been designed and built at the Rm. Valcea National Research and Development Institute for Cryogenics and Isotopic Technologies t...
-
Technical Reviewers Fusion Science and Technology, 2023 Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-12-08
Published in Fusion Science and Technology (Vol. 80, No. 1, 2024)
-
The Radiation Impact of Delayed Photoneutron Production in ITER Components Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-12-05 R. Pampin, A. Cubi, N. Taylor, M. Fabbri, P. Martinez-Albertos, P. Sauvan, Y. LeTonqueze
Photoneutrons may be generated in beryllium by energetic gamma rays via the reaction 9Be(γ,n)8Be. In ITER, the beryllium layer of the first wall may be the source of such photoneutrons. During plas...
-
Fault Prediction of Molecular Pump Based on DE-Bi-LSTM Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-11-29 Yang Zhou, Ming Jiang, Xiaolin Yuan, Guizhong Zuo, Yue Chen, Jilei Hou, Kai Jia, Peng Liu, Zhixin Cheng
A molecular pump is a high vacuum acquisition piece of equipment that provides a clean vacuum environment for the Experimental Advanced Superconducting Tokamak (EAST) device. Its running state affe...
-
Isotope Exchange of ND3 on Pt Catalyst–Loaded 5A Molecular Sieve Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-11-30 Paul R. Beaumont, Daniel M. Clairmonte
Recollecting and purifying unburned tritium is a preferred process for D-T fusion operations. However, tritium containing byproducts act as a potential holdup for the material, requiring additional...
-
Investigations on 3He: Hydrogen Isotope Separation Employing Palladium/Silver Membranes Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-11-17 Gheorghe Bulubasa, Alina Niculescu, George Ana, Ciprian Bucur, Iuliana Ștefan, Maria Crăciun, Anisia Bornea
Tritium resulting from separation processes is being stored in metal hydrides. In time, because of radioactive decay, tritium converts into 3He, which accumulates in the storage vessel. The recover...
-
Phenomena Identification and Ranking Table for Thermal-Hydraulic Safety of China Fusion Engineering Test Reactor Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-11-17 Jinghua Jiang, Yuanchen Qin, Lili Tong, Xuewu Cao, Songlin Liu, Xiaoman Cheng
The China Fusion Engineering Test Reactor (CFETR) is presently in the engineering design phase, and it is crucial to establish a thermal-hydraulic safety analysis method. First of all, the identifi...
-
Integration of a Micro-Channel Reactor in a CECE Process for H2 Removal from the O2 Stream Produced by the H2 Generator Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-11-17 Alina Niculescu, Gheorghe Bulubașa, George Ana, Ciprian Bucur, Maria Crăciun, Anisia Bornea
A hydrogen generator is used in the combined electrolysis catalytic exchange process (CECE) for low-level tritiated water detritiation as a source of H2 (Q2) for the liquid-phase catalytic exchange...
-
Hard X-ray Measurement with LaBr3 Detector for the Study of Runaway Electrons on the HL-2M Tokamak Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-11-09 Jinwen Zhang, Wei Zhao, Zuowei Wen, Lei Feng, Li Zhao, Lingfeng Wei, Xiang Chen, Guoliang Yuan
Runaway electrons (REs) generated during disruptions pose a significant safety threat to tokamaks, as they can melt and damage the plasma-facing components (PFCs). Therefore, studying RE behavior i...
-
Study on Tritium Permeation from the Primary to the Secondary Water Coolant for Fusion Reactors Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-11-09 Akito Ipponsugi, Kazunari Katayama, Taku Matsumoto, Shogo Iwata, Makoto Oya, Youji Someya
Several fusion plants plan to utilize two high-temperature and high-pressurized water coolant systems. Because of the high hydrogen-isotope mobility in high-temperature metal, tritium will inevitab...
-
Current Tracking and Circulating Current Suppression Super-Twisting Sliding Mode Control for Parallel Operation of EAST Fast Control Power Supply Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-11-06 Haihong Huang, Zhao Chen, Haixin Wang
To quickly output sufficient current for plasma excitation control, parallel operation of a structure of multiple branches is adopted in the Experimental Advanced Superconducting Tokamak (EAST) fas...
-
Thoughts on the H-Bomb Decision, Oppenheimer’s Loyalty/Security Hearing, and Vacating of the AEC Decision Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-11-06 T. E. Mason
This summer’s release of Oppenheimer, the major Hollywood movie by Christopher Nolan, has brought renewed attention to J. Robert Oppenheimer’s thoughts, concerns, and intentions regarding the U.S. ...
-
High Heat Flux Testing of Brazed W/CuCrZr Monoblock in High Heat Flux Test Facility Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-10-30 Kedar Bhope, Vinay Menon, Sunil Belsare, Samir Khirwadkar, Rajamannar Swamy, Mayur Mehta, Premjit Singh Kongkham, Tushar Patel, Nikunj Patel, Prakash Mokariya
The Institute for Plasma Research (IPR) is involved in the development of various technologies for fabrication and testing/qualification of tungsten (W)–based plasma-facing components for ITER-like...
-
The First Calculation of Comptonization Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-10-30 Jonathan I. Katz
The first calculation of energy exchange between electrons and the radiation field by inverse Compton and Compton recoil was reported by Hurwitz in Los Alamos Reports LA-301 (1945) and LA-553 (1946...
-
Synthesis of Erbium Deuterides via Deuterium Ion Implantation into Erbium Thin Films Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-10-26 J. Northall, M. S. B. Darby, A. Cooper, A. Hollingsworth, Y. Zayachuk, A. Wohlers, A. Simons, H. Smith
An experimental study of a synthesis technique in which deuterium ions are implanted into thin films of erbium to form erbium deuterides is presented. Results from thermal desorption spectroscopy i...
-
Possibilities of Reprocessing Solid Waste with Tritium from Fusion Using High-Temperature Heating Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-10-23 Jaroslav Stoklasa, Jan Hrbek, Lucie Karásková Nenadálová, Bence Mészáros, Mykhaylo Paukov
This study evaluates the types of waste generated by tritium during nuclear fusion. Some methods of reprocessing and decontaminating solid waste using thermal processes are evaluated, and the advan...
-
Design, Fabrication, and Test of a Prototype of Matrix Heat Exchanger for Cryogenic Distillation of Hydrogen Isotopes Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-10-24 Claudia Bogdan, Sebastian Brad, Horia Necula, Oleksandr Sirosh, Catalin Brill, Mihai Vijulie, Alin Lazar, Aleksandr Grafov
The following properties are needed to increase the efficiency of refrigeration, liquefaction, and cryogenic separation cycles: Heat exchangers must have high effectiveness doubled by high compactn...
-
Modeling the Tokamak Exhaust Processing System in a Commercial Simulator for Process Monitoring Purposes Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-10-24 Eduardo Iraola, José M. Nougués, Lluís Batet, Josep A. Feliu, Luis Sedano
Nuclear fusion depends on tritium breeding and self-sufficiency. Tritium represents a hazard due to its radioactivity and migration properties. Because of these difficulties, ITER, the largest fusi...
-
Microdispersed Ti/B/N Materials Synthesized in Chain Reactions in Processes Initiated by Microwaves of a High-Power Gyrotron: Structure and Cytotoxicity Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-10-23 Nina N. Skvortsova, Ekaterina A. Obraztsova, Vladimir D. Stepakhin, Evgeny M. Konchekov, Tatiana E. Gayanova, Lilja A. Vasilieva, Dmitrii A. Lukianov, Andrey V. Sybachin, Dmitry A. Skvortsov, Namik G. Gusein-Zade, Oleg N. Shishilov
An original plasma-chemical facility has been developed at the Prokhorov General Physics Institute of the Russian Academy of Sciences based on the gyrotrons of the thermonuclear complex of the L-2 ...
-
Thermal Effects on Dynamic Behavior of CFETR Vacuum Vessel Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-10-13 Songbo Han, Xiaojun Ni, Jian Ge, Jinxin Sun
The vacuum vessel (VV) of the China Fusion Engineering Test Reactor (CFETR) was designed to withstand the variable structural loads resulting from dynamic excitation, such as seismic and plasma dis...
-
Parameter Space Constraints for Compact Spherical Tokamak Fusion Reactors Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-10-09 P. N. Maya, S. P. Deshpande
Parameter space for spherical tokamak reactors is explored quantitatively to elucidate the main constraints for spherical tokamak design choices. Using a constant plasma current Ip search constrain...
-
Foreword: Special issue featuring papers from the 25th Topical Meeting on the Technology of Fusion Energy (TOFE 2022) Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-10-05 Arkady Serikov
Published in Fusion Science and Technology (Vol. 79, No. 8, 2023)
-
Interaction of the Substance of the Tsarev Meteorite with Radiation from a Powerful Gyrotron: Dusty Plasma Cloud Formation and Phase Transformations Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-09-19 Nailya S. Akhmadullina, Valentin D. Borzosekov, Nina N. Skvortsova, Vladimir D. Stepakhin, Namik G. Gusein-Zade, Dmitriy V. Malakhov, Alexander V. Knyazev, Tatiana E. Gayanova, Anastasiya K. Kozak, Alexander S. Sokolov, Karen A. Sarksyan, Aleksey V. Ishchenko, Ilya A. Weinstein, Victor I. Grokhovsky, Oleg N. Shishilov
A new approach for simulation of the interaction of space and lunar dust with the surface of spacecrafts has been proposed. The approach is based on creating a dusty plasma cloud when the substance...
-
ViMA – The Spinning Rotor Gauge to Measure the Viscosity of Tritium Between 77 and 300 K Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-09-19 Johanna Wydra, Alexander Marsteller, Robin Größle, Florian Priester, Michael Sturm
Experimental values for the viscosity of the radioactive hydrogen isotope tritium (T2) are currently unavailable in literature. The value of this material property over a wide temperature range is ...
-
Auto-Recording System for Long-Pulse Negative Ion–Based Neutral Beam Injection Experimental Data Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-09-19 Y. Li, C. D. Hu, Y. Z. Zhao, S. H. Song, Y. H. Xie, Y. Gu, Z. Wang, T. Ban, Q. L. Cui
For long-pulse negative ion–based neutral beam injection (NNBI) experiments, an automatic recording system was designed. The data processing algorithm of neutral beam injection was implemented on t...
-
Optimization of Wall-Conditioning Techniques on the MT-II Tokamak Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-09-14 Muhammad Abdullah, Ahmad Ali, Riaz Khan, Osama Abdur Rehman, Zia-ur- Rehman, Shahab Ud-Din Khan, Sehrish Shakir, Shahzaib Zahid, Muhammad Ismail, Rafaqat Ali, Sarfraz Ahmad, Shahid Hussain
Abstract The MT-II is a small spherical tokamak that is currently under construction at the Pakistan Tokamak Plasma Research Institute. Wall conditioning of the MT-II vacuum vessel (VV) is an essential step to achieve a good quality vacuum for plasma experiments. This study presents an overview of the wall-conditioning techniques implemented on the MT-II VV, including baking and glow discharge cleaning
-
Construction of a Test Facility and the Test of an Active Tritium Permeation Barrier Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-09-14 Joshua Kohpeiss, Stefan Welte, Ion Cristescu, Nancy Tuchscherer
Abstract In future fusion or fission reactors, tritium permeation may present a serious challenge. In order to separate the water steam cycle from gas streams containing significant amounts of tritium, a permeation barrier is necessary. Tritium permeation into the environment through steam generators and heat exchangers can be a significant hazard regarding radiation and environmental safety. In the
-
Machine Learning–Based Prediction of Irradiation-Induced Swelling from Synergistic Effects of Helium and Hydrogen Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-09-08 Huajiang Jin, Shuaishuai Zhang, Jianxiang Zheng, Jian Zhang, Huifang Miao, Liuxuan Cao
Abstract Understanding irradiation-induced degradation processes of nuclear structural materials is essential for creating methodologies and procedures for nuclear reactor safety. Due to the time- and resource-intensive property of both experiments and multiscale simulations of irradiation damage, the trial-and-error approach is completely inefficient. Recently, machine learning techniques have been
-
Presentation and Preliminary Test of APRIL: A New Facility for the Characterization of Antipermeation Coatings for Fission and Fusion Applications Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-09-07 Francesca Papa, Alessandro Venturini, Marco Utili, Gianfranco Caruso, Alessandro Tassone, Mariano Tarantino
Abstract Antipermeation and anticorrosion coatings are being developed to reduce tritium permeation from liquid metal [LiPb of the water-cooled lithium-lead breeding blanket and Pb for lead-cooled fast reactors (LFRs)] to primary heat transfer systems. The facility APRIL (Alumina-coating for tritium Permeation Reduction for Innovative LFR) was designed and installed at ENEA Brasimone R.C. to characterize
-
Influence of AZ61 Filler Composition on Grain Refinement of Mg-Al-Zn Alloy GTA Welds Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-09-07 N. Kishore Babu, Gopi Krishna C, K. Vamsi Krishna, Ateekh Ur Rehman, Prakash Srirangam
Abstract The enhancement of mechanical properties in welds is heavily reliant on grain refinement. This study aims to investigate the impact of the addition of AZ61 filler and the impact of the absence of filler on the macrostructure and microstructure, as well as the mechanical properties, of Mg-Al-Zn alloy (AZ31) gas tungsten arc (GTA) welds. The AZ61 filler was employed to introduce a higher concentration
-
Organically Bound Tritium Activity Level in Plants During Growing Season and Environmental Factor Influences Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-09-05 Irina Vagner, Carmen Varlam, Ionut Făurescu, Denisa Făurescu, Diana Bogdan
Abstract This paper presents the activity level of total organically bound tritium (OBT) in different plant species, e.g., grains (wheat, corn), trees (apple, fir), and vines, and different organs of the plants (buds, leaves, fruits, straw, and branches) surrounding the Experimental Pilot Plant for Tritium and Deuterium Separation during the growing seasons of 2020 and 2021, The influence of environmental
-
Proof-of-Concept Modeling for the Use of Neutron Reflectometry for the In-Situ Diagnosis of Deuterium Accumulation in Tungsten and Dispersion-Strengthened Tungsten Alloys Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-09-05 Matthew S. Parsons, Carli S. Smith, Camilo Jaramillo-Correa, Jean Paul Allain
Abstract The diagnosis of plasma-facing components in a fusion environment is challenging due to the limited number of measurement techniques that have been developed for in situ surface analysis. In this work, we assess the feasibility of using neutron reflectometry (NR) for the in situ diagnosis of deuterium accumulation in tungsten and dispersion-strengthened tungsten alloys. TRIM is used to simulate
-
New Achievements of H2-HD-D2 Isotopic Separation with the Cryogenic Distillation Experimental Stand from ICSI Cryogenic Laboratory Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-08-31 Sebastian Brad, Mihai Vijulie, Alin Lazar, Claudia Bogdan, Oleksandr Sirosh, Catalin Brill, Aleksandr Grafov, Anișoara Oubraham, Alina Niculescu, George Bulubasa
Abstract In the design process of a cryogenic distillation plant for the separation of hydrogen isotopes, two main objectives, often impossible to achieve simultaneously, are taken into account: a high separation factor for different mixtures and isotope concentrations and the reduction of design, manufacturing, and operating costs with increased efficiency and safety. All this should result from the
-
The Serendipitous Discovery of the New Elements Einsteinium and Fermium from the Debris of the Mike Thermonuclear Test Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-08-31 Stephen Allan Becker
Abstract On October 31, 1952, the United States successfully detonated the Los Alamos Mike thermonuclear device on the surface of Elugelab Island at Eniwetok Atoll in the Pacific Ocean. This test was the first demonstration of a high-yield thermonuclear explosion on Earth. The 10.4-Mt device yield obliterated Elugelab Island and left a 6240-ft-diameter underwater crater. Later, radiochemical analysis
-
Architecture Design and Internal Implementation of a Universal Coupling Between Controllers and Physics in a Tokamak Flight Simulator Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-08-30 Chuanren Wu, Pierre David, Emiliano Fable, Domenico Frattolillo, Luigi Emanuel Di Grazia, Massimiliano Mattei, Mattia Siccinio, Wolfgang Treutterer, Hartmut Zohm
Abstract The flight simulator predicts the dynamic behavior of a full plasma discharge (described in terms of one-dimensional profiles) by employing multiple control loops based on synthetic diagnostics, which could also emulate realistic sensor and actuator models. It serves as a valuable tool for designing and optimizing plasma scenarios, as well as for assessing the feasibility of controlling discharges
-
Foreword Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-08-29 Lynne Goodwin, Tana Morrow, Brian M. Patterson
Published in Fusion Science and Technology (Vol. 79, No. 7, 2023)
-
Deuterium Stream Management Leaving the LPCE Column in a CECE Process for Heavy Water Detritiation Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-08-29 Musharaf Rabbani, Anthony Busigin, Haiqin Mao, Nisa Halsey, Dayna La Barbera
Abstract In heavy water detritiation using the combined electrolysis and catalytic exchange (CECE) process, deuterium leaving the electrolyzer is fed to the bottom of the liquid-phase catalytic exchange column (LPCE) in which tritium exchanges between the tritiated deuterium gas (moving upward in the LPCE column) and D2O liquid (moving downward in the LPCE column). Once the deuterium gas leaves the
-
Organic Vacuum Pump Fluids for the Vacuum Pumping of Fusion Power Plants Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-08-29 Tyler Guin, Kori McDonald, James Folkert, Chris Verst, Jay Gaillard, Timothy A. DeVol, Valery N. Bliznyuk, George Larsen
Abstract Vacuum pumps are the heart of the fusion fuel cycle, but most currently proposed pumping technologies are not capable of handling the required flow rates and vacuum pressures. Oil-containing vacuum pumps can readily meet the flow requirements, but vacuum fluids will degrade in fusion-relevant environments due to contact with tritium and exposure to high-energy radiation. Here, we describe
-
The Impact of Disruptions on the Economics of a Tokamak Power Plant Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-08-23 Andrew D. Maris, Allen Wang, Cristina Rea, Robert Granetz, Earl Marmar
Abstract Tokamaks are often considered to be a leading candidate for near-term, cost-effective fusion energy, but these devices are susceptible to sudden loss of confinement events called disruptions. The threat of disruptions has garnered serious attention in research for the next generation of burning plasma experiments, such as ITER, but has received little treatment in economic studies of magnetic
-
Study of the Effective Torus Exhaust High Vacuum Pumping System Performance in the Inner Tritium Plant Loop of EU-DEMO Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-08-23 Tim Teichmann, Xueli Luo, Thomas Giegerich, Christian Day
Abstract The requirement for a reduction of the tritium inventory of the European demonstration fusion reactor (EU-DEMO) has led to the active research and development of a continuously working pumping process termed “KALPUREX.” This process foresees the direct recycling of a large fraction of the unburnt hydrogen isotopologues via superpermeation in metal foil pumps during the burn phase. The remaining
-
High-Energy Tritium Ion and α-Particle Release from the Near-Surface Layer of Lithium During Neutron Irradiation in the Nuclear Reactor Core Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-08-17 Erlan Batyrbekov, Mendykhan Khasenov, Mazhyn Skakov, Yuriy Gordienko, Kuanysh Samarkhanov, Andrey Kotlyar, Alexandr Miller, Vadim Bochkov
Abstract This paper examines in situ spectroscopic measurements of nuclear-excited plasma of noble gases excited by 6Li(n,α)3H nuclear reaction products in the core of a nuclear reactor. A thin layer of lithium applied on the walls of the experimental device, stabilized in the matrix of the capillary-porous structure, serves as a source of gas excitation. During in-pile tests conducted at the IGR research
-
Effects of Neutron Source Models on Neutron Wall Loading in the EAST Tokamak Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-08-17 Wenjun Yang, Changlin Lan, Guoqiang Li, Xueyu Gong, Xiang Gao
Abstract As a significant input for neutronics analysis of tokamak devices, the plasma neutron source is a bridge connecting fusion plasma physics and engineering design. A plasma neutron source model is established based on the EAST plasma configuration. The maximum neutron wall loading (NWL) is near the outboard midplane and is more than ~20% that of the inboard midplane. The investigations demonstrate
-
Material Plasma Exposure eXperiment High Heat Flux Microwave Absorber Design, Manufacture, and Articles Test Fusion Sci. Technol. (IF 0.9) Pub Date : 2023-08-17 A. Hussain, V. Rao, N. Branch, T. Gray, A. Kubik, A. Aaron, K. Logan, S. Stewart, A. Lumsdaine, G. S. Showers, R. L. Romesberg, D. E. Wolfe
The Material Plasma Exposure eXperiment (MPEX) at Oak Ridge National Laboratory is in the final design phase. MPEX will be capable of exposing neutron-irradiated materials to plasmas for the study ...