Nuclear Science and Technology Open Research最新文献

Compact, energy efficient neutron source: Enabling Technology for Thorium Breeder and Accelerator Transmutation of Waste 紧凑、节能的中子源：钍育成器和加速器嬗变废物的使能技术

Nuclear Science and Technology Open Research Pub Date : 2024-08-08 DOI: 10.12688/nuclscitechnolopenres.17567.1

A. Hershcovitch, Thomas Roser

{"title":"Compact, energy efficient neutron source: Enabling Technology for Thorium Breeder and Accelerator Transmutation of Waste","authors":"A. Hershcovitch, Thomas Roser","doi":"10.12688/nuclscitechnolopenres.17567.1","DOIUrl":"https://doi.org/10.12688/nuclscitechnolopenres.17567.1","url":null,"abstract":"Background To fulfill need for large flux neutron sources, presently utilized and/or proposed large flux neutron sources are either nuclear reactor based or accelerator based. First method has shortcomings: in radioactive waste generation high proliferation risk. Accelerator based spallation neutron sources are complex, expensive and use large amounts of power. Method A novel neutron source comprising of a deuterium beam (energy of about 100 KeV) injected into a tube filled with tritium gas and/or tritium plasma that generates D-T fusion reactions, whose products are 14.06 MeV neutrons and 3.52 MeV alpha particles, is described. At the opposite end of the tube, the energy of deuterium ions that did not interact was recovered. Beryllium walls of appropriate thickness can be utilized to absorb 14 MeV neutrons and release 2 – 3 low-energy neutrons. Each ion source and tube forms a module. Larger systems can be formed using multiple units. Results Calculations indicate that this method is feasible and has multiple advantages. Relevance: among the possible applications of this neutron source concept are subcritical nuclear breeder reactors and transmutation of radioactive waste. Conclusion Due to its simplicity the idea can be tested using an inexpensive tabletop experiment.","PeriodicalId":475854,"journal":{"name":"Nuclear Science and Technology Open Research","volume":"49 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141926572","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Tensile and creep properties of small specimens of reduced-activation ferritic steel F82H, and the correlation to standard specimen data 还原活化铁素体钢 F82H 小试样的拉伸和蠕变特性，以及与标准试样数据的相关性

Nuclear Science and Technology Open Research Pub Date : 2024-07-26 DOI: 10.12688/nuclscitechnolopenres.17514.1

Takuya Nagasaka, Jingjie Shen, Masami Ando, Taichiro Kato, Takashi Nozawa, H. Tanigawa

{"title":"Tensile and creep properties of small specimens of reduced-activation ferritic steel F82H, and the correlation to standard specimen data","authors":"Takuya Nagasaka, Jingjie Shen, Masami Ando, Taichiro Kato, Takashi Nozawa, H. Tanigawa","doi":"10.12688/nuclscitechnolopenres.17514.1","DOIUrl":"https://doi.org/10.12688/nuclscitechnolopenres.17514.1","url":null,"abstract":"Background A reduced-activation ferritic/martensitic (RAFM) steel, F82H steel, is the primary candidate structural material for fusion reactor blanket. Small specimen test technique is essential to develop the blanket materials using limited irradiation volume in high flux neutron field. An international collaboration activity “Towards the Standardization of Small Specimen Test Techniques for Fusion Applications” has been initiated under the framework of the International Atomic Energy Agency Coordinated Research Project for Phase I from 2017 to 2021, and Phase II from 2022 to 2026. The present paper reports the preliminary results on tensile and creep tests as a summary of the above Phase I activity. Methods Tensile and creep tests were conducted at 550 and 650°C, using flat-plate SSJ type small specimens with various gauge thickness ranged from 0.14 to 1.2 mm, while gauge length and width are 5 and 1.2 mm, respectively. In addition, round bar type standard specimens with a gauge geometry of 6 mm in diameter and 30 mm in length was also tested for comparison. Results Tensile yield stress, ultimate tensile strength and uniform elongation were independent of the gauge thickness of SSJ specimens, and agreed with the data from the standard size specimens. On the other hand, total elongation was decreased with decreasing the thickness. In creep tests, rupture time was decreased with decreasing the gauge thickness of SSJ specimens. Standard size specimens exhibited shorter rupture time than the SSJ specimens. Conclusions The SSJ type specimens provided similar tensile parameters to those from the standard specimen, except total elongation. Creep rupture time of the SSJ specimens were different from the standard specimen, and decreased with decreasing the gauge thickness.","PeriodicalId":475854,"journal":{"name":"Nuclear Science and Technology Open Research","volume":"19 25","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-07-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141801081","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

A theory and analysis of the impact of gas in the dynamical behavior of the molten salt research reactor leading to the computation of the "gas coefficients of reactivity" 熔盐研究反应堆动力学行为中气体影响的理论和分析，从而计算 "气体反应系数"

Nuclear Science and Technology Open Research Pub Date : 2024-05-10 DOI: 10.12688/nuclscitechnolopenres.17428.1

Terry Price, Kevin Clarno, Ondrej Chvala

{"title":"A theory and analysis of the impact of gas in the dynamical behavior of the molten salt research reactor leading to the computation of the \"gas coefficients of reactivity\"","authors":"Terry Price, Kevin Clarno, Ondrej Chvala","doi":"10.12688/nuclscitechnolopenres.17428.1","DOIUrl":"https://doi.org/10.12688/nuclscitechnolopenres.17428.1","url":null,"abstract":"Background Molten salt reactors, and other types of circulating, liquid fueled, nuclear reactors contain a certain amount of gas entrained in their liquid nuclear fuel. This gas induces an effect on the nuclear and dynamical behavior of the reactor as a whole. Gas voids respond to variation in temperature and pressure differently than liquids. When the gas voids in the reactor working fluid expand, the nuclear fuel is pushed from the core. Likewise, when the gas voids contract, more nuclear fuel enters into the core. Methods This paper examines the interplay of gas void fraction and reactivity in a molten salt reactor, and attempts to elucidate the dynamical response of the void fraction and the reactivity of the system to perturbation in system temperature, pressure, and gas quantity. A theory is presented that aims at describing the relationship between reactivity and gas behavior. This theory is then applied to the Molten Salt Research Reactor (MSRR) design, a facility currently under construction at Abilene Christian University campus. Results A result of this paper is the temperature and void fraction parameterized gas coefficients of reactivity for the Molten Salt Research Reactor. Conclusions The presence of voids accounts for 5-30% of the total temperature coefficient of reactivity, demonstrating their non-trivial contribution. Additionally, the study emphasizes the importance of considering gas content in MSR physics, especially in the context of pressure transients and system reactivity during pump trips. The initial system pressure, particularly in designs like the MSRR operating at sub-atmospheric pressures, is crucial due to its influence on reactivity changes during rapid pressure increases.","PeriodicalId":475854,"journal":{"name":"Nuclear Science and Technology Open Research","volume":" 54","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-05-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140991467","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

A literature review of pyroprocessing safeguards 高温处理保障措施文献综述

Nuclear Science and Technology Open Research Pub Date : 2024-04-24 DOI: 10.12688/nuclscitechnolopenres.17524.1

Abigayle I. Hargreaves, Eva Barker, Jaylyn Berry, Evan Dolley, Chad L. Pope

{"title":"A literature review of pyroprocessing safeguards","authors":"Abigayle I. Hargreaves, Eva Barker, Jaylyn Berry, Evan Dolley, Chad L. Pope","doi":"10.12688/nuclscitechnolopenres.17524.1","DOIUrl":"https://doi.org/10.12688/nuclscitechnolopenres.17524.1","url":null,"abstract":"Pyroprocessing is a promising technology for reprocessing used nuclear fuel (UNF) from light water reactors (LWR) and sodium fast reactors (SFR). With the advancement of fast reactors with projects from companies such as TerraPower, the prospects of pyroprocessing are more promising than ever before, as fast reactors can consume all actinides, not just uranium and plutonium. Before pyroprocessing can be implemented commercially, pre-existing safeguards used for aqueous reprocessing must be adapted for pyroprocessing. Safeguards, as determined by both the Nuclear Regulatory Commission (NRC) and the International Atomic Energy Agency (IAEA), are discussed in this review as guidelines for approaches used in both domestic and international reprocessing plants. The implementation of safeguards in aqueous reprocessing was then reviewed based on the experience from existing aqueous facilities. The experimental pyroprocessing facilities were identified as pyroprocessing plants in the design stage with one operating exception of the Fuel Conditioning Facility (FCF). The safeguard methods implemented or designed for each and the accompanying challenges of utilizing existing safeguards in pyroprocessing are considered and a summary of applicable approaches is included.","PeriodicalId":475854,"journal":{"name":"Nuclear Science and Technology Open Research","volume":"50 3","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-04-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140662294","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Risk-Informed Performance-Based methods for cyber-attack on nuclear power facilities 针对核电设施网络攻击的基于风险的绩效方法

Nuclear Science and Technology Open Research Pub Date : 2024-04-08 DOI: 10.12688/nuclscitechnolopenres.17523.1

Andrew Gisondi, Camille J. Palmer

{"title":"Risk-Informed Performance-Based methods for cyber-attack on nuclear power facilities","authors":"Andrew Gisondi, Camille J. Palmer","doi":"10.12688/nuclscitechnolopenres.17523.1","DOIUrl":"https://doi.org/10.12688/nuclscitechnolopenres.17523.1","url":null,"abstract":"A new approach is described that offers a Risk-Informed Performance-Based (RIPB) framework for quantifying the risk associated with a cyber-attack on a nuclear power-generating facility. The first part of the method involves 1) the creation of a simplified 10 CFR 73.54 compliant cyber infrastructure, 2) modeling of design basis threats against the network and passive defense of the network and 3) applying the model metrics as inputs into a Bayesian analysis to calculate the exploit probability of a plant controller. The RAVEN code package was used to perform a stochastic calculation to quantify the aleatory uncertainty associated with exploiting a plant controller and produce basic statistics associated with those outputs, such as the standard deviation and standard error. Other tools, such as ADAPT, were also explored, which could be leveraged for direct DPRA analysis of network topology, such that new failure modes or initiating events could be discovered. The second aspect of the RIPB method considers the impact of the controller on the physical plant. This evaluation was conducted by postulating an accident scenario possibly caused by the dynamics of an exploited process controller, initiating that event in a RELAP5 model controlled by the RAVEN risk analysis package, and demonstrating the types of algorithms that can be used to quantify the consequences of the accident scenario. The new two-part method explored in this work provides the uncertainty associated with a cyber-initiating event and the associated consequences of a postulated accident resulting from that exploit, as well as example tools and algorithms for performing the analysis.","PeriodicalId":475854,"journal":{"name":"Nuclear Science and Technology Open Research","volume":"27 13","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-04-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140728254","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Deployment of small modular reactors in the European Union 在欧洲联盟部署小型模块化反应堆

Nuclear Science and Technology Open Research Pub Date : 2024-03-14 DOI: 10.12688/nuclscitechnolopenres.17510.1

Kamil Števanka, Ondrej Chvala

引用次数: 0

Development and evaluation of parallel simulated annealing algorithm for reactor core optimization problems 针对反应堆堆芯优化问题的并行模拟退火算法的开发与评估

Nuclear Science and Technology Open Research Pub Date : 2024-02-12 DOI: 10.12688/nuclscitechnolopenres.17464.1

Jake Mikouchi-Lopez, G. Delipei, Jason Hou

{"title":"Development and evaluation of parallel simulated annealing algorithm for reactor core optimization problems","authors":"Jake Mikouchi-Lopez, G. Delipei, Jason Hou","doi":"10.12688/nuclscitechnolopenres.17464.1","DOIUrl":"https://doi.org/10.12688/nuclscitechnolopenres.17464.1","url":null,"abstract":"One of the significant issues in contemporary international politics is to examine the contexts of energy usage of different countries, keeping in mind the looming climate threat. Energy transition not only highlights the central role of energy usage but also exposes the vulnerability caused by it. Given the context, Bangladesh has adopted nuclear technology to meet its economic demand and environmental requirements. As a middle-income country, eyeing to graduate to a developing nation by 2041, its choice of exploring nuclear energy has exposed the country to the question of the rationality of the decision. Nuclear energy has a distinguished history that accommodates several debates about its safety and sustainability. Though many developed countries are planning for a nuclear phase-out, Bangladesh’s decision merits attention and explanation to embrace such a stand. Often, the economic priorities have been attached to Bangladesh’s decision for the energy transition, while the discussion about nuclear energy in Bangladesh ignores the geopolitical purposes and international political agenda. This paper, therefore, aims to explore the internal and external climate-related urgency, and geopolitical concerns responsible for such a transition, which have remained unexplored in the existing literature.","PeriodicalId":475854,"journal":{"name":"Nuclear Science and Technology Open Research","volume":"56 12","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-02-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139844725","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Development and evaluation of parallel simulated annealing algorithm for reactor core optimization problems 针对反应堆堆芯优化问题的并行模拟退火算法的开发与评估

Nuclear Science and Technology Open Research Pub Date : 2024-02-12 DOI: 10.12688/nuclscitechnolopenres.17464.1

Jake Mikouchi-Lopez, G. Delipei, Jason Hou

{"title":"Development and evaluation of parallel simulated annealing algorithm for reactor core optimization problems","authors":"Jake Mikouchi-Lopez, G. Delipei, Jason Hou","doi":"10.12688/nuclscitechnolopenres.17464.1","DOIUrl":"https://doi.org/10.12688/nuclscitechnolopenres.17464.1","url":null,"abstract":"One of the significant issues in contemporary international politics is to examine the contexts of energy usage of different countries, keeping in mind the looming climate threat. Energy transition not only highlights the central role of energy usage but also exposes the vulnerability caused by it. Given the context, Bangladesh has adopted nuclear technology to meet its economic demand and environmental requirements. As a middle-income country, eyeing to graduate to a developing nation by 2041, its choice of exploring nuclear energy has exposed the country to the question of the rationality of the decision. Nuclear energy has a distinguished history that accommodates several debates about its safety and sustainability. Though many developed countries are planning for a nuclear phase-out, Bangladesh’s decision merits attention and explanation to embrace such a stand. Often, the economic priorities have been attached to Bangladesh’s decision for the energy transition, while the discussion about nuclear energy in Bangladesh ignores the geopolitical purposes and international political agenda. This paper, therefore, aims to explore the internal and external climate-related urgency, and geopolitical concerns responsible for such a transition, which have remained unexplored in the existing literature.","PeriodicalId":475854,"journal":{"name":"Nuclear Science and Technology Open Research","volume":"29 12","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-02-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139784849","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Design of an optimized nuclear fuel pellet 优化核燃料芯块的设计

Nuclear Science and Technology Open Research Pub Date : 2024-01-09 DOI: 10.12688/nuclscitechnolopenres.17443.1

Patricia Dooley, Dakota Contryman, Addie Hervey, Robert Ivers, Isabella Reddish, Yuze Song

{"title":"Design of an optimized nuclear fuel pellet","authors":"Patricia Dooley, Dakota Contryman, Addie Hervey, Robert Ivers, Isabella Reddish, Yuze Song","doi":"10.12688/nuclscitechnolopenres.17443.1","DOIUrl":"https://doi.org/10.12688/nuclscitechnolopenres.17443.1","url":null,"abstract":"Background The design of an improved nuclear fuel pellet for use in the Westinghouse AP1000 reactor that is more powerful than existing pellets, is less expensive to manufacture, and meets Nuclear Regulatory Commission requirements for certification was undertaken to complete a senior design course in the ABET-certified nuclear engineering curriculum of Rensselaer Polytechnic Institute, Troy, NY. Methods The modeling team selected the Monte Carlo N-Particle (MCNP) program for assessing how well the pellet design achieves a k-effective value of 1, designed the base model consisting of a fuel pin inside a boron-water moderator with reflector, and ran MCNP tests on the base pellet. The design team modified the base pellet and tested it at different uranium-235 enrichments, with void spheres of varying volume and silicon carbide inclusions in the void volume. The simulation team selected K-code for testing the fuel pellets. The economics team analyzed the cost of manufacturing the improved pellet from cost of raw material through its tail assay in the form of Separative Work Unit (SWUs). The impacts team researched environmental, societal, governmental, political, and public affairs aspects of nuclear fuel production. Results Multiple configurations of uranium enrichment and silicon carbide volume inclusions in the nuclear fuel pellet achieved a k eff of 1, and the price per pellet, assuming fabrication costs comparable to existing manufacturing processes, was reduced by as much as about 50% when the volume of uranium oxide replaced by silicon carbide is 0.27 cm3. At smaller replacement volumes, the price per pellet is reduced by as little as 5%. Conclusions The goal of designing an optimized fuel pellet was met. Replacing a 0.27 cm3-volume sphere of uranium oxide with silicon carbide from the center of a pellet of 4%, 5%, or 6% uranium-235 enrichment reduced the cost of the pellet by approximately 50%.","PeriodicalId":475854,"journal":{"name":"Nuclear Science and Technology Open Research","volume":"51 18","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-01-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139441852","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Covert system for detecting nuclear dirty bombs in public venues 探测公共场所核脏弹的隐蔽系统

Nuclear Science and Technology Open Research Pub Date : 2024-01-09 DOI: 10.12688/nuclscitechnolopenres.17455.1

Matthew Niichel, Mary Brackett, Brant Purcell, Douglas Gologorsky, Ben Werve

{"title":"Covert system for detecting nuclear dirty bombs in public venues","authors":"Matthew Niichel, Mary Brackett, Brant Purcell, Douglas Gologorsky, Ben Werve","doi":"10.12688/nuclscitechnolopenres.17455.1","DOIUrl":"https://doi.org/10.12688/nuclscitechnolopenres.17455.1","url":null,"abstract":"Background In the past two decades, the potential threat of a radiological dispersal device (RDD) or “dirty bomb,” which combines conventional explosives with radioactive material, has been a concern for counterterrorism efforts. The accessibility of radioactive materials used in various applications, such as medicine, industry, and research, makes RDDs a viable weapon of choice for terrorists. While the radiation released from an RDD is generally not lethal beyond a short range, the long-term health, environmental, and psychological effects of radiation release will have an impact on the future of a society. Providing proactive security measures will aid in the deterrence of potential radiological terrorist threats. Methods The use of commercial off-the-shelf detectors and GPS modules can be integrated with software to provide the approximate location of a radioactive anomaly. With the strategic placement of a circular array of 4-inch × 4-inch Thallium dopped Sodium-Iodide (NaI) in a façade of a full trashcan, it is possible to determine if, when, and the general direction of a hand- carried threat entering a venue. A supplemental detector containing a Cesium-Iodide (CsI) crystal and a GPS module fitted to a plate carrier vest can further refine the location of a threat. In tandem, these two designs are capable of providing the RDD screening that is currently lacking in public. Conclusions While a true threat may contain a radiation source well in the hundreds of Curies, the designs selected are tested and calibrated to 1-microcurie button sources. Which provides scaled results that indicate the possibility for the deployment of such a detection scheme in a venue. Although the devices tested are limited by commercial GPS resolution, the ability for both designs to determine the presence and approximate location of a button source within 10 feet is promising for further larger scale tests.","PeriodicalId":475854,"journal":{"name":"Nuclear Science and Technology Open Research","volume":"41 9","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-01-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139442368","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0