Atomic Energy最新文献_第10页

Testing of a transportation and storage container model 测试运输和储存集装箱模型

IF 0.4 4区工程技术

Atomic Energy Pub Date : 2024-04-09 DOI: 10.1007/s10512-024-01045-3

V. V. Abramov, A. G. Kazantsev, O. M. Petrov, A. E. Buchelnikov, I. A. Kochura, V. P. Kravchenko, R. S. Sedov, V. V. Tausenev, M. V. Radchenko, M. V. Kharin

引用次数: 0

Fire simulation in the main control room of Bushehr nuclear power plant using CFAST software 使用 CFAST 软件模拟布什尔核电站主控室的火灾情况

IF 0.4 4区工程技术

Atomic Energy Pub Date : 2024-04-09 DOI: 10.1007/s10512-024-01071-1

Sahar Mojab, Ehsan Zarifi, Saeed Zare Ganjaroodi, Gholamreza Jahanfarnia

{"title":"Fire simulation in the main control room of Bushehr nuclear power plant using CFAST software","authors":"Sahar Mojab, Ehsan Zarifi, Saeed Zare Ganjaroodi, Gholamreza Jahanfarnia","doi":"10.1007/s10512-024-01071-1","DOIUrl":"10.1007/s10512-024-01071-1","url":null,"abstract":"<div><p>Fire protection is one of the most important issues to ensure safety and reduce risks of nuclear power plants. The main control room (MCR) is one of the parts of a nuclear power plant that is often identified with a high risk of fire in safety assessments. Although robust programs to shut down commercial reactors in any fires have been successfully maintained, the purpose of this paper is to simulate the fire in the MCR of Bushehr nuclear power plant unit‑1 (BNPP-1) using CFAST software. CFAST is a two-zone fire model used to calculate the evolving distribution of smoke, fire gases, and temperature throughout the compartments of a building during a fire. The data required for simulation have been extracted from final safety analysis reports and operating documents of BNPP‑1 and NUREG6850 reports. The results showed that the highest recorded temperature was related to the upper part of the standing cabinet about 1013 °C, which is the result of flames as well as heat transfer through smoke. Also, the other highest recorded temperature was in the lower part of the standing cabinet about 700 °C. Finally, the first ventilation system was closed for about 350 s and the second ventilation system was closed for about 860 s after the fire started.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"134 5-6","pages":"391 - 396"},"PeriodicalIF":0.4,"publicationDate":"2024-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140585557","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

Neutronic investigation of ALFRED lead-Cooled fast reactor core using monte carlo modeling 利用蒙特卡洛模型对 ALFRED 铅冷快堆堆芯进行中子研究

IF 0.4 4区工程技术

Atomic Energy Pub Date : 2024-04-09 DOI: 10.1007/s10512-024-01054-2

Saeed Zare Ganjaroodi, Ehsan Zarifi

引用次数: 0

Features of coolant movement at the boundary of jacketless fuel assemblies with fuel rods of various diameters 带有不同直径燃料棒的无护套燃料组件边界冷却剂运动的特点

IF 0.4 4区工程技术

Atomic Energy Pub Date : 2024-04-09 DOI: 10.1007/s10512-024-01048-0

V. V. Lemekhov, V. I. Solonin, V. G. Krapivtsev, S. I. Getya, P. V. Markov, S. G. Kutychkin

引用次数: 0

Optimization of the square and squared-off cascades to separate stable isotopes using meta-heuristic algorithms 利用元启发式算法优化用于分离稳定同位素的方形级联和方形级联

IF 0.4 4区工程技术

Atomic Energy Pub Date : 2024-04-09 DOI: 10.1007/s10512-024-01072-0

Fatemeh Ardestani, Jaber Safdari, Mohammad Hassan Mallah, Morteza Imani

{"title":"Optimization of the square and squared-off cascades to separate stable isotopes using meta-heuristic algorithms","authors":"Fatemeh Ardestani, Jaber Safdari, Mohammad Hassan Mallah, Morteza Imani","doi":"10.1007/s10512-024-01072-0","DOIUrl":"10.1007/s10512-024-01072-0","url":null,"abstract":"<div><p>In this paper, the optimization of the square and squared-off cascades for the separation of stable isotopes with a certain number of gas centrifuges (GCs) using particle swarm optimization (PSO) and the whale optimization algorithm (WOA) was studied. For this purpose, the “SC-PSO” and “SC-WOA” codes for the square cascade (SC), and the “SOC-PSO” and “SOC-WOA” codes for the squared-off cascade (SOC) were developed. The performance of the PSO and WOA algorithms in the optimization of the square and squared-off cascades as an example for the separation of <sup>124</sup>Xe from nine stable isotopes of xenon up to an enrichment of 85% was compared. The recovery coefficient of <sup>124</sup>Xe isotope by the codes “SC-PSO”, “SC-WOA”, “SOC-PSO”, and “SOC-WOA” was obtained 86.14, 78.11, 92.84, and 83.41% respectively. The performance of the algorithms indicates the higher yield of the PSO algorithm in the optimization of SC and SOC. The efficiency of the PSO has been demonstrated by the Griewank test function compared with the WOA, the sine cosine algorithm (SCA), and the dragon-fly algorithm (DA) (PSO>WOA>SCA>DA). Furthermore, the results show that SOC performs better than SC.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"134 5-6","pages":"397 - 416"},"PeriodicalIF":0.4,"publicationDate":"2024-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140585612","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

KIR-TG code for interconnected thermo-hydraulic and neutron-physical test calculations of VVER-SKD reactors 用于 VVER-SKD 反应堆热液和中子物理试验计算的 KIR-TG 代码

IF 0.4 4区工程技术

Atomic Energy Pub Date : 2024-04-05 DOI: 10.1007/s10512-024-01059-x

V. I. Belousov, V. D. Davidenko, I. I. Dyachkov, N. N. Elkin, M. R. Malkov, M. V. Ioannisian, M. G. Chernetskii, A. A. Chernitskaya, V. G. Zborovskii, V. V. Likhanskii, O. V. Khoruzhii

{"title":"KIR-TG code for interconnected thermo-hydraulic and neutron-physical test calculations of VVER-SKD reactors","authors":"V. I. Belousov, V. D. Davidenko, I. I. Dyachkov, N. N. Elkin, M. R. Malkov, M. V. Ioannisian, M. G. Chernetskii, A. A. Chernitskaya, V. G. Zborovskii, V. V. Likhanskii, O. V. Khoruzhii","doi":"10.1007/s10512-024-01059-x","DOIUrl":"10.1007/s10512-024-01059-x","url":null,"abstract":"<div><p>The paper considers the KIR-TG software package, which is designed for the interconnected neutron-physical and thermohydraulic test calculations of the infinite grid of VVER-SKD fuel elements. As part of the work, a software program written in the Python and Lua dynamic programming languages for linking between the module for calculating neutron physics (KIR computer program) and the TK-SKD thermohydraulic module was created and applied. The use of precision calculation performed by the Monte Carlo method in the neutron-physical part avoids the error of deterministic approximation methods in the calculation results. The problem statement, as well as the nature and results of the work, revealed the advantages of this approach to solving problems related to thermal-hydraulic calculations: parallel neutronic and sequential thermal-hydraulic calculations do not affect the overall speed of the associated calculation, the calculation codes are developed in parallel to save time and resources, and errors are tracked separately.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"134 5-6","pages":"305 - 311"},"PeriodicalIF":0.4,"publicationDate":"2024-04-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140582222","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

Numerical simulation of a hydrogen leakage in a ventilated room 通风房间氢气泄漏的数值模拟

IF 0.4 4区工程技术

Atomic Energy Pub Date : 2024-04-04 DOI: 10.1007/s10512-024-01067-x

K. S. Kutuzova, V. V. Stakhanov, E. V. Bezgodov, Yu. A. Tomilov, I. A. Popov, S. D. Pasyukov, A. A. Tarakanov

引用次数: 0

Preparation for dismantling the liquid waste disposal system of MR and RFT research reactors 准备拆除 MR 和 RFT 研究堆的液体废物处理系统

IF 0.4 4区工程技术

Atomic Energy Pub Date : 2024-04-04 DOI: 10.1007/s10512-024-01066-y

A. G. Volkovich, O. P. Ivanov, V. I. Kolyadin, A. V. Lemus, V. I. Pavlenko, L. A. Ryazanova, S. G. Semenov, E. A. Stepanov, A. V. Chesnokov, A. D. Shisha

{"title":"Preparation for dismantling the liquid waste disposal system of MR and RFT research reactors","authors":"A. G. Volkovich, O. P. Ivanov, V. I. Kolyadin, A. V. Lemus, V. I. Pavlenko, L. A. Ryazanova, S. G. Semenov, E. A. Stepanov, A. V. Chesnokov, A. D. Shisha","doi":"10.1007/s10512-024-01066-y","DOIUrl":"10.1007/s10512-024-01066-y","url":null,"abstract":"<div><p>The article presents the results of a radiation survey carried out on the liquid radioactive waste disposal system of decommissioned MR and RFT research reactors. The system is located in the buildings adjacent to the dismantled reactor building on the territory of the Kurchatov Institute national research center. The results of the visual and radiation survey carried out on the equipment and premises of the disposal system for liquid radioactive waste will inform the development of design documentation for its elimination. Following the removal of liquid radioactive waste from storage tanks, the equipment and building structures at this location should be dismantled. The carrying out of recommended works will complete the decommissioning of MR and RFT research reactors. Further, the site of the reactor buildings and their auxiliary systems will be rehabilitated to achieve a radiation situation that meets the sanitary and hygienic standards for the group B personnel.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"134 5-6","pages":"361 - 366"},"PeriodicalIF":0.4,"publicationDate":"2024-04-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140582215","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

Magnetic insulation system for a laser-plasma ion diode of a portable neutron generator 便携式中子发生器激光等离子体离子二极管的磁绝缘系统

IF 0.4 4区工程技术

Atomic Energy Pub Date : 2024-04-04 DOI: 10.1007/s10512-024-01064-0

D. S. Stepanov, K. I. Kozlowski, A. P. Skripnik, E. Y. Shkolnikov

{"title":"Magnetic insulation system for a laser-plasma ion diode of a portable neutron generator","authors":"D. S. Stepanov, K. I. Kozlowski, A. P. Skripnik, E. Y. Shkolnikov","doi":"10.1007/s10512-024-01064-0","DOIUrl":"10.1007/s10512-024-01064-0","url":null,"abstract":"<div><p>A new promising type of portable pulsed neutron generator is based on a laser-plasma ion diode with magnetic insulation. At the present stage of its evolution, such a generator requires the development of a magnetic insulation system capable of blocking secondary electrons in a laser-plasma diode. The article considers the development of such a magnetic insulation system, during which the effect of the magnetic field distribution on the shape of the ion current pulse through the diode was estimated using the KARAT electromagnetic code to significantly enhance the theoretical validity of the magnetic system design. The final design of the magnetic system should provide the complete insulation of secondary electrons, as well as significantly increase the fraction of ions deposited on the neutron target, as well as the electrical strength of the accelerating gap. Following was fabrication of the developed magnetic system, measurements of the magnetic field distribution within the accelerating gap showed the sufficient accuracy of its implementation. The average difference with the model is ~3%.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"134 5-6","pages":"346 - 351"},"PeriodicalIF":0.4,"publicationDate":"2024-04-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140582246","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

Experimental study of the hydrogen leakage and ignition in a ventilated room 通风房间氢气泄漏和点火实验研究

IF 0.4 4区工程技术

Atomic Energy Pub Date : 2024-04-04 DOI: 10.1007/s10512-024-01068-w

K. S. Kutuzova, V. V. Stakhanov, E. V. Bezgodov, D. A. Mastyuk, I. A. Popov, S. D. Pasyukov, A. A. Tarakanov

引用次数: 0