Pub Date : 2024-08-08DOI: 10.12688/nuclscitechnolopenres.17567.1
A. Hershcovitch, Thomas Roser
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.
{"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}
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.
{"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}
Pub Date : 2024-05-10DOI: 10.12688/nuclscitechnolopenres.17428.1
Terry Price, Kevin Clarno, Ondrej Chvala
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.
{"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}
Pub Date : 2024-04-24DOI: 10.12688/nuclscitechnolopenres.17524.1
Abigayle I. Hargreaves, Eva Barker, Jaylyn Berry, Evan Dolley, Chad L. Pope
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.
{"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}
Pub Date : 2024-04-08DOI: 10.12688/nuclscitechnolopenres.17523.1
Andrew Gisondi, Camille J. Palmer
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.
{"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}
Pub Date : 2024-03-14DOI: 10.12688/nuclscitechnolopenres.17510.1
Kamil Števanka, Ondrej Chvala
This paper was written after the beginning of the 2022 energy and security crisis in Europe, which forced the national state governments as well as the European Union (EU) to reexamine environmental and energy strategies. The paper focuses on the role that small modular reactors (SMRs) may play as a part of a medium and long-term solution to this unprecedented situation. The history of EU climate policies and the current energy situation in the EU is broadly examined. The paper explores the potential energy, national security, and environmental benefits of nuclear power, along with its possible contribution to a net-zero economy. The main focus of the study, involving discussions with experts in the United States (US), was on the development of SMR-specific regulations, as well as the progress of SMR deployment projects in the US. The discussion explores SMR deployment challenges and potential solutions, in terms of policy recommendations applicable for the EU and its member states, in case a rapid SMR deployment becomes politically desirable.
{"title":"Deployment of small modular reactors in the European Union","authors":"Kamil Števanka, Ondrej Chvala","doi":"10.12688/nuclscitechnolopenres.17510.1","DOIUrl":"https://doi.org/10.12688/nuclscitechnolopenres.17510.1","url":null,"abstract":"This paper was written after the beginning of the 2022 energy and security crisis in Europe, which forced the national state governments as well as the European Union (EU) to reexamine environmental and energy strategies. The paper focuses on the role that small modular reactors (SMRs) may play as a part of a medium and long-term solution to this unprecedented situation. The history of EU climate policies and the current energy situation in the EU is broadly examined. The paper explores the potential energy, national security, and environmental benefits of nuclear power, along with its possible contribution to a net-zero economy. The main focus of the study, involving discussions with experts in the United States (US), was on the development of SMR-specific regulations, as well as the progress of SMR deployment projects in the US. The discussion explores SMR deployment challenges and potential solutions, in terms of policy recommendations applicable for the EU and its member states, in case a rapid SMR deployment becomes politically desirable.","PeriodicalId":475854,"journal":{"name":"Nuclear Science and Technology Open Research","volume":"3 2","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-03-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140242506","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}
Pub Date : 2024-02-12DOI: 10.12688/nuclscitechnolopenres.17464.1
Jake Mikouchi-Lopez, G. Delipei, Jason Hou
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.
{"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}
Pub Date : 2024-02-12DOI: 10.12688/nuclscitechnolopenres.17464.1
Jake Mikouchi-Lopez, G. Delipei, Jason Hou
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.
{"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}
Pub Date : 2024-01-09DOI: 10.12688/nuclscitechnolopenres.17443.1
Patricia Dooley, Dakota Contryman, Addie Hervey, Robert Ivers, Isabella Reddish, Yuze Song
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%.
背景 为完成纽约州特洛伊市伦斯勒理工学院（Rensselaer Polytechnic Institute, Troy, NY）经 ABET 认证的核工程课程中的一门高级设计课程，设计了一种用于西屋 AP1000 反应堆的改进型核燃料芯块，它比现有芯块的功率更大，制造成本更低，并符合核管理委员会的认证要求。方法 建模小组选择了蒙特卡洛 N 粒子（MCNP）程序来评估燃料芯块设计实现 1 k 效值的情况，设计了由硼水慢化剂和反射器内的燃料芯块组成的基础模型，并对基础燃料芯块进行了 MCNP 测试。设计小组修改了基础燃料芯块，并在不同铀-235 浓度下进行了测试，测试中使用了不同体积的空隙球和空隙中的碳化硅夹杂物。模拟小组选择 K 代码来测试燃料芯块。经济学小组分析了从原材料成本到以分离工作单位（SWU）形式进行的尾部化验的改进型燃料芯块的制造成本。影响小组对核燃料生产的环境、社会、政府、政治和公共事务等方面进行了研究。结果 核燃料芯块中铀浓缩和碳化硅体积夹杂物的多种配置实现了 k 效率为 1，假定制造成本与现有制造工艺相当，当碳化硅替代的氧化铀体积为 0.27 立方厘米时，每块芯块的价格降低了约 50%。如果替代量较小，则每个燃料颗粒的价格可降低 5%。结论 设计优化燃料芯块的目标已经实现。在铀-235 丰度为 4%、5% 或 6% 的燃料芯块中心用碳化硅替代 0.27 立方厘米体积的氧化铀球时，燃料芯块的成本降低了约 50%。
{"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}
Pub Date : 2024-01-09DOI: 10.12688/nuclscitechnolopenres.17455.1
Matthew Niichel, Mary Brackett, Brant Purcell, Douglas Gologorsky, Ben Werve
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.
{"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}
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