Atomic Energy最新文献_第6页

Effects of Novovoronezh NPP-2 industrial development on the assessment of the external radiation dose to personnel 新沃罗涅日核电厂-2工业发展对人员外辐射剂量评估的影响

IF 0.3 4区工程技术

Atomic Energy Pub Date : 2025-05-28 DOI: 10.1007/s10512-025-01213-z

S. N. Krasnoperov, D. A. Pripachkin, D. V. Tulinov, A. D. Danilov

引用次数: 0

Aerodynamic model based on similarity numbers and computational fluid dynamics for coolant mixing in HTGR bottom plenum 基于相似数和计算流体力学的高温堆底充气室内冷却剂混合气动模型

IF 0.3 4区工程技术

Atomic Energy Pub Date : 2025-05-28 DOI: 10.1007/s10512-025-01204-0

A. A. Dobrov, S. M. Dmitriev, D. V. Doronkov, M. A Legchanov, A. V. Ryazanov, D. V. Didenko, O. L. Nikanorov, V. V. Petrunin, S. A. Rogozhkin

引用次数: 0

System for measuring low flow rates of aggressive and radioactive liquids in radiochemical industry 放射化学工业中腐蚀性和放射性液体低流速测量系统

IF 0.3 4区工程技术

Atomic Energy Pub Date : 2025-05-28 DOI: 10.1007/s10512-025-01209-9

A. A. Denisevich, A. G. Goryunov, S. N. Liventsov, G. V. Sumin, I. S. Nadezhdin

引用次数: 0

Prospects of artificial intelligence in nuclear industry 人工智能在核工业中的应用前景

IF 0.3 4区工程技术

Atomic Energy Pub Date : 2025-05-28 DOI: 10.1007/s10512-025-01215-x

A. A. Andrianov, A. A. Zaluzhnyy, A. V. Mitskevich, A. V. Ponomarev, P. B. Ptitsyn

引用次数: 0

Modes of generating pulsed discharges in chambers with inertial electrostatic plasma confinement 惯性静电等离子体约束室中产生脉冲放电的模式

IF 0.3 4区工程技术

Atomic Energy Pub Date : 2025-05-28 DOI: 10.1007/s10512-025-01211-1

S. P. Maslennikov, Yu. V. Mikhailov, I. A. Prokuratov

引用次数: 0

Calculation of a cascade with the same number of gas centrifuges in stages and a given concentration of the target isotope in output streams 在输出流中给定目标同位素浓度的条件下，等量气体离心机级联的计算

IF 0.3 4区工程技术

Atomic Energy Pub Date : 2025-05-28 DOI: 10.1007/s10512-025-01210-2

V. A. Palkin

引用次数: 0

Analytical simulation of sustainable development scenarios for global two-component nuclear power industry. Part 1. Thermal reactor scenarios 全球双组份核电工业可持续发展情景分析模拟。第1部分。热反应堆方案

IF 0.3 4区工程技术

Atomic Energy Pub Date : 2025-05-19 DOI: 10.1007/s10512-025-01187-y

A. V. Abramova, V. V. Kharitonov

{"title":"Analytical simulation of sustainable development scenarios for global two-component nuclear power industry. Part 1. Thermal reactor scenarios","authors":"A. V. Abramova, V. V. Kharitonov","doi":"10.1007/s10512-025-01187-y","DOIUrl":"10.1007/s10512-025-01187-y","url":null,"abstract":"<div><h3>Background</h3><p>The share of nuclear power in global electricity production has fallen from 17 to 9% since 2000. Moreover, the issue of limited natural uranium resources and their availability for the industry becomes acute.</p><h3>Aim</h3><p>To analytically determine the possibilities of accelerated and sustainable development of global nuclear power industry (NPI) based on thermal nuclear reactors.</p><h3>Materials and methods</h3><p>Scenarios for the accelerated development of global NPI based on thermal reactors were calculated using analytical methods developed by the authors for predicting the dynamics of natural uranium resource depletion.</p><h3>Results and discussion</h3><p>The paper provides the development dynamics of NPI with only thermal reactors of a VVER type and its share in the global electricity production. Given the uranium reserves for currently operating reactors, 7.9 MtU of existing natural uranium resources appear sufficient to build only 490 (290) reactors with an operating period of 60 (80) years. Doubling natural uranium resources to 16 MtU and increasing the annual rate of thermal reactor construction to 4% could increase the contribution of nuclear power plants to the global electricity generation from 9 to 11–12% by 2035, yet followed with a rapid decline as uranium is depleted.</p><h3>Conclusion</h3><p>The performed analysis demonstrates inadequacy of a long-term and sustainable development for global NPI based only on thermal nuclear reactors. An analysis of development scenarios based on fast reactors will be presented in Part 2.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"137 3-4","pages":"137 - 146"},"PeriodicalIF":0.3,"publicationDate":"2025-05-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145167147","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Thermal-hydraulic model of the heavy liquid metal coolant—steam-water mixture flow 重液态金属冷却液-蒸汽-水混合物流动的热-水力模型

IF 0.3 4区工程技术

Atomic Energy Pub Date : 2025-05-19 DOI: 10.1007/s10512-025-01188-x

A. V. Mitskevich, A. O. Popov, A. S. Gritsai

{"title":"Thermal-hydraulic model of the heavy liquid metal coolant—steam-water mixture flow","authors":"A. V. Mitskevich, A. O. Popov, A. S. Gritsai","doi":"10.1007/s10512-025-01188-x","DOIUrl":"10.1007/s10512-025-01188-x","url":null,"abstract":"<div><h3>Background</h3><p>Reactors with heavy liquid metal coolant (HLMC) based on a eutectic lead-bismuth alloy (Pb-Bi) require a safety justification. The latter includes the obligatory simulation of normal operating and emergency modes using thermal-hydraulic calculation codes.</p><h3>Aim</h3><p>To develop a one-dimensional three-field model for the joint flow of three fluids including HLMC, steam, and water for a KORSAR/LMR-based software tool numerically simulating in detail physical processes in reactor plants during inter-circuit leaks with water coolant ingress into HLMC.</p><h3>Materials and methods</h3><p>The KORSAR/LMR thermal-hydraulic code developed by the Alexandrov Research Institute of Technology was used for calculations; validation was performed using published experimental data of the LIFUS 5 facility.</p><h3>Results and discussion</h3><p>In the course of the study, we have modified the system of conservation equations, flow mode and heat exchange maps, as well as changed an approach to closing relations. The calculated pressure dynamics of the three-field model turned out to be closer to the experimental one as compared to the two-field model consisting of HLMC and steam-gas mixture.</p><h3>Conclusion</h3><p>A three-field one-dimensional model of the joint flow for three fluids has been developed and implemented in a new software tool based on the KORSAR/LMR computer code. This software can be used for the predictive safety analysis of reactor plants with HLMC. Model correlations can be further refined due to the expansion of the experimental base.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"137 3-4","pages":"147 - 153"},"PeriodicalIF":0.3,"publicationDate":"2025-05-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145167149","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Justification of a protective container for a Tc-99m generator Tc-99m发电机防护容器的论证

IF 0.3 4区工程技术

Atomic Energy Pub Date : 2025-05-01 DOI: 10.1007/s10512-025-01193-0

N. V. Kuznetsov, O. Yu. Kochnov, D. V. Stepchenkov, V. V. Fomichev

{"title":"Justification of a protective container for a Tc-99m generator","authors":"N. V. Kuznetsov, O. Yu. Kochnov, D. V. Stepchenkov, V. V. Fomichev","doi":"10.1007/s10512-025-01193-0","DOIUrl":"10.1007/s10512-025-01193-0","url":null,"abstract":"<div><h3>Background</h3><p>In nuclear medicine, radiopharmaceutical drugs (RPDs) containing the technetium isotope Tc-99m are used to treat oncological diseases, such as brain, thyroid, and salivary gland cancer, as well as for diagnostic studies of the cardiovascular system. These RPDs are created using a molybdenum-technetium Tc-99m generator.</p><h3>Aim</h3><p>To determine the main parameters of complex protection for a designed transport container of a technetium generator for the production of RPDs in accordance with the GMP standard.</p><h3>Materials and methods</h3><p>Eighteen container material options were considered. To assess the protective characteristics of the container, we used the MicroShield v. 8.01 software. Transport indices and categories of all container options were determined taking into account the calculated rate of equivalent doses for gamma radiation from the Mo-99/Tc-99m sorption column and the nominal source activity.</p><h3>Results</h3><p>We have simulated an advanced protective container for the Tc-99m generator. The best protective characteristics are noted for the option combining tungsten and lead 2.5 and 3.5 cm thick, respectively.</p><h3>Conclusion</h3><p>This complex design of the protective container ensures the safe operation and transportation of the Tc-99m generator.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"137 3-4","pages":"180 - 189"},"PeriodicalIF":0.3,"publicationDate":"2025-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145160736","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Testing of the CABARET-COMBUSTION CFD code using data from experiments on accelerated combustion of hydrogen-air mixtures in a Big Mock-up Tube facility 利用大型模拟管道设施中氢气-空气混合物加速燃烧实验数据对CABARET-COMBUSTION CFD代码进行测试

IF 0.3 4区工程技术

Atomic Energy Pub Date : 2025-04-23 DOI: 10.1007/s10512-025-01200-4

A. I. Gavrikov, A. V. Danilin, E. V. Bezgodov, S. D. Pasyukov, V. A. Simonenko

{"title":"Testing of the CABARET-COMBUSTION CFD code using data from experiments on accelerated combustion of hydrogen-air mixtures in a Big Mock-up Tube facility","authors":"A. I. Gavrikov, A. V. Danilin, E. V. Bezgodov, S. D. Pasyukov, V. A. Simonenko","doi":"10.1007/s10512-025-01200-4","DOIUrl":"10.1007/s10512-025-01200-4","url":null,"abstract":"<div><h3>Background</h3><p>Issues of hydrogen explosion safety are extremely relevant. Search for solutions requires both experimental and computational methods.</p><h3>Aim</h3><p>To experimentally study the turbulent combustion of hydrogen-air mixtures and to test the CABARET-COMBUSTION CFD calculation code using the obtained data.</p><h3>Materials and methods</h3><p>The study includes experiments conducted in a facility representing a large diameter pipe, as well as numerical simulation of deflagration combustion.</p><h3>Results</h3><p>The calculated data on the flame front propagation velocity and pressure dynamics at the shock wave front are consistent with experimental results.</p><h3>Conclusion</h3><p>The obtained results indicate the potential of using the CABARET-COMBUSTION CFD code in the numerical solution of hydrogen-air mixture combustion problems. This code and its testing on data obtained with high-quality diagnostics will increase the predictive capabilities of supercomputer simulation for the analysis of hypothetical accidents at a qualitatively new level.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"137 3-4","pages":"241 - 249"},"PeriodicalIF":0.3,"publicationDate":"2025-04-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145167945","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0