Progress in Nuclear Energy最新文献

{"title":"Preliminary analysis of startup and acceleration transient characteristics of helium-xenon cooled reactor direct brayton cycle system","authors":"Haoyang Liao ,&nbsp;Fulong Zhao ,&nbsp;Hui Bao ,&nbsp;Ruibo Lu ,&nbsp;Sichao Tan ,&nbsp;Puzhen Gao ,&nbsp;Ruifeng Tian","doi":"10.1016/j.pnucene.2024.105462","DOIUrl":"10.1016/j.pnucene.2024.105462","url":null,"abstract":"<div><div>Helium-xenon cooled reactor direct Brayton cycle system has excellent application prospects in small nuclear power plants due to its light weight, high compactness and simple structure. The safe startup of reactor system is very important, so the system startup scheme is designed. In addition, reactor system may be affected by external acceleration during operation. Whether reactor system can operate normally and safely after being affected by acceleration and its influence characteristics are not clear. In order to verify the feasibility of the system startup scheme and explore the acceleration influence characteristics, the system analysis program was developed to simulate the system startup transient operating conditions and the transient operating conditions of reactor system under the influence of acceleration. In the research of acceleration influence characteristics, acceleration has different periods, amplitudes, types and directions, and the load state is divided into load change with system output power and constant load. The results show that the designed system startup scheme can start reactor system safely. Reactor system can ignore the influence of acceleration when it has load change with system output power ability. If the load remains constant, reactor system cannot ensure continuous and stable operation after being affected by acceleration, which has the risk of Loss of Flow Accident (LOFA). The relevant research results provide theoretical reference and support for the design of the reactor system startup scheme and the research on the influence characteristics of acceleration on reactor system.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105462"},"PeriodicalIF":3.3,"publicationDate":"2024-09-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142323522","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Chlorination of HALEU regulus casting dross","authors":"Guy L. Fredrickson,&nbsp;Brennan C. Mohr,&nbsp;Michael N. Patterson","doi":"10.1016/j.pnucene.2024.105464","DOIUrl":"10.1016/j.pnucene.2024.105464","url":null,"abstract":"<div><div>A scoping study was performed for chlorinating dross formed during uranium casting operations. The purpose is to minimize the losses of uranium to dross wastes. The dross is primarily a mixture of uranium metal and uranium oxide with a minor fraction of crucible and crucible coating materials. The reaction chemistries were performed in a carrier salt of LiCl-KCl eutectic at 500 °C. The addition of FeCl₂ chlorinated the uranium metal to UCl₃, by reducing the FeCl₂ to iron metal. After the uranium metal was chlorinated, zirconium metal was added to the salt. The residual FeCl₂ chlorinated the zirconium metal to ZrCl₄, by reducing the FeCl₂ to iron metal. In turn, the ZrCl₄ chlorinated the uranium oxide to UCl₃, by converting the ZrCl₄ to zirconium oxide. The effectiveness of the chlorination reactions was qualitatively verified by cyclic voltammograms that indicated the presence or absence of FeCl₂ and UCl₃ in the salt.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105464"},"PeriodicalIF":3.3,"publicationDate":"2024-09-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142323521","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Depressurization strategy of China's advanced pressurized water reactor under typical accidents","authors":"Ji Xing ,&nbsp;Pei Yu ,&nbsp;Zhaoming Meng ,&nbsp;Dufeng Lv ,&nbsp;Zhengrun Shang ,&nbsp;Zhongning Sun","doi":"10.1016/j.pnucene.2024.105459","DOIUrl":"10.1016/j.pnucene.2024.105459","url":null,"abstract":"<div><div>Advanced pressurized water reactor was simulated using system analysis program. The depressurization strategy for the automatic depressurization system (ADS) under typical ADS-triggering accidents (2-inch/10-inch cold leg break, inadvertent opening of the ADS, DVI pipeline break) was investigated. The results show that after these accidents, ADS can ensure the operation of the three types of safe injection tanks, with high redundancy and inherent safety. The multi-stage design of ADS aids the sparger in maintaining a stable critical jet state. In 10-inch cold leg break accident, the sparger cannot reached the critical jet state under all of pipeline fault conditions. From a system point of view, adjusting the pipeline design of ADS is necessary to avoid long-term condensation oscillation of the sparger in some accidents. From a design perspective of the local equipment, the nozzle structure of the sparger should attenuate the dynamic load caused by the condensation oscillation and back-attack phenomenon.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105459"},"PeriodicalIF":3.3,"publicationDate":"2024-09-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142323524","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Nuclear fuel qualification: History, current state, and future","authors":"Mitchell Mika ,&nbsp;Allison Probert ,&nbsp;Assel Aitkaliyeva","doi":"10.1016/j.pnucene.2024.105460","DOIUrl":"10.1016/j.pnucene.2024.105460","url":null,"abstract":"<div><div>The qualification of nuclear fuel is the process by which a fuel is certified for use within a reactor design. This process involves massive technical and procedural coordination across multiple private and public institutions with long project completion timelines. The current frameworks published in literature do not address the roles of private reactor developers in the qualification process, nor the regulatory requirements that form the background for fuel qualification. These roles and requirements are not static and have evolved throughout the development of the commercial nuclear industry. UO₂ fuel, the only fuel considered fully qualified today, achieved its status in large part due to its early selection and rapid deployment under a still developing regulatory landscape. Today, fuel qualification efforts must operate within modern regulatory realities, which will require extensive testing and model development. Building on the existing fuel qualification frameworks, we define the optimal roles of the parties involved with fuel qualification. We also suggest viewing experimental efforts through a data-centric perspective in which parallel improvements can be made in collection, processing, and storage to facilitate quicker qualification timelines. These efforts then promote advanced modeling efforts, such as mechanistic modeling and digital twin development.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105460"},"PeriodicalIF":3.3,"publicationDate":"2024-09-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142323520","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Shutdown dose rate calculation for fission reactors: An application of the MS-CADIS method to OPAL","authors":"B. Marcinkevicius,&nbsp;C. Fedon","doi":"10.1016/j.pnucene.2024.105448","DOIUrl":"10.1016/j.pnucene.2024.105448","url":null,"abstract":"<div><div>There have been considerable advances of shutdown dose rate (SDDR) calculation methods for fusion related problems, however applications of these methods in the fission reactor field have hitherto been sparse. The present study attempts to bridge this gap by investigating the applicability of SDDR calculation methods for fission reactor problems. Specifically, we aim to assess and validate whether recent advances in SDDR methods can be successfully applied in fission research reactors. To this end, we estimate the shutdown dose rate distribution at the Open Pool Australian Light water reactor (OPAL) using the rigorous two step (R2S) computational method, and we compare the calculated results with the experimental data. This method utilizes a 3D reactor model implemented in the Monte Carlo N-Particle (MCNP) transport code, the AutomeD VAriaNce reduction Generator (ADVANTG) code for geometry discretization and variance reduction calculations, and the Oak Ridge Isotope GENeration (ORIGEN) inventory code for activation calculations. To ensure robustness, we employ two variance reduction techniques, Forward Weighted Consistent Adjoint Driven Importance Sampling (FW-CADIS) and Multi-Step Consistent Adjoint Driven Importance Sampling (MS-CADIS). To the best of our knowledge, this is the first MS-CADIS method implementation for fission reactor problems. The SDDR is estimated at ten locations within the experimental hall, all situated more than 4 m away from the reactor core.</div><div>The paper shows that, the experimental observations are within the lower and upper bounds of the simulation results for 4 out of 10 locations, while the remaining observations are within a factor of 7, with one significant outlier. The calculated average dose rate is within 5% of the nominal values of the experimental observations for 3 locations. The computational results are within statistical uncertainty by using two different variance reduction techniques, with significant computational advantage of MS-CADIS over FW-CADIS for SDDR calculations. The results indicate that the combination of SDDR distribution maps, estimated dose rate energy dependance, and activation information are powerful tools in identifying the radioisotopes and reactor components dominating the SDDR. These results can contribute to better radiation safety practices in contaminated areas, by enabling the minimal dose path planning or by improving radiation shielding.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105448"},"PeriodicalIF":3.3,"publicationDate":"2024-09-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142319936","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Verifications and applications of NECP-Bamboo2.0 for PWR whole-core multi-cycle pin-by-pin simulation","authors":"Sicheng Wang,&nbsp;Yunzhao Li,&nbsp;Junwei Qin,&nbsp;Yilin Liang,&nbsp;Yuancheng Zhou,&nbsp;Liangzhi Cao,&nbsp;Hongchun Wu","doi":"10.1016/j.pnucene.2024.105447","DOIUrl":"10.1016/j.pnucene.2024.105447","url":null,"abstract":"<div><div>In 2018, the NECP Laboratory at Xi'an Jiaotong University (XJTU) published the pin-by-pin two-step calculation code system NECP-Bamboo2.0 for the physics analysis of Pressurized Water Reactors (PWRs). Previously, NECP-Bamboo2.0 was primarily verified for its neutronics analysis capabilities. The code system has recently been enhanced for practical reactor physics analysis of commercial PWR cores. In this paper, several modifications of NECP-Bamboo2.0 regarding its improvement in functionality are introduced. Then, the pin-by-pin calculation capability of the code system was verified using the 2D and 3D VERA benchmark problems. Comparisons with reference solutions provided by high-fidelity codes demonstrated the computational accuracy of NECP-Bamboo2.0. Additionally, NECP-Bamboo2.0 was applied to the multi-cycle physics analysis of two commercial PWR cores, CNP300 and CNP1000. Comparisons with the measurements regarding the startup physics tests and the depletion processes illustrate the reliability of NECP-Bamboo2.0 in practical pin-by-pin reactor physics analysis and highlight the improvements of the pin-by-pin method over the assembly-homogenized coarse-mesh diffusion method.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105447"},"PeriodicalIF":3.3,"publicationDate":"2024-09-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142314724","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Optical and gamma-ray shielding properties of calcium sodium borate glasses with varied equal concentrations of ZnO and BaO","authors":"M.I. Sayyed ,&nbsp;Nabasu Seth Ezra ,&nbsp;Iskandar Shahrim Mustafa ,&nbsp;K.K. Dakok ,&nbsp;M. Rashad ,&nbsp;Yasser Maghrbi","doi":"10.1016/j.pnucene.2024.105451","DOIUrl":"10.1016/j.pnucene.2024.105451","url":null,"abstract":"<div><div>This study presents the optical and radiation shielding characteristics of a newly developed borate glass, doped with equal quantities of ZnO and BaO, and modified with calcium and sodium. The glass samples were prepared using the melt quenching technique, with the composition formula (80-x-y)B₂O₃-10CaO-10Na₂O-xZnO-yBaO, where x and y were varied at 5, 10, 15, and 20 mol%. Comprehensive analyses of the optical and gamma shielding properties were carried out using UV–visible spectrophotometry and Phy-X software, respectively. The UV–visible spectroscopic data allowed for the calculation of various parameters including the direct and indirect optical energy band gaps, refractive index, dielectric constants, and polarizability. It was observed that the direct optical energy band gap decreased from 3.91 to 3.10 eV, while the indirect band gap fell from 3.41 to 2.91 eV with increasing ZnO and BaO content. Conversely, the refractive index rose from 2.29 to 2.42 with higher concentrations of ZnO and BaO. The linear attenuation coefficients (LACs) across the range of 0.015–15 MeV exhibited an inverse relationship. Among the glass samples, B40Zn20Ba20 exhibited the lowest tenth value layer (TVL) and the highest effective atomic number (Zeff), indicating its superior performance as a radiation shielding material. Overall, the produced glass samples demonstrate commendable properties for both optical applications and radiation shielding.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105451"},"PeriodicalIF":3.3,"publicationDate":"2024-09-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S0149197024004013/pdfft?md5=cee1d69d9886f1635b396a7acef525ec&pid=1-s2.0-S0149197024004013-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142312488","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"A Proposed Non-Intrusive System for the Verification of Sensitive Nuclear Material","authors":"M. Ibrahim ,&nbsp;W. El-Gammal ,&nbsp;M. Darweesh ,&nbsp;N. Mostafa ,&nbsp;M. Mohsen","doi":"10.1016/j.pnucene.2024.105456","DOIUrl":"10.1016/j.pnucene.2024.105456","url":null,"abstract":"<div><div>One of the primary challenges in negotiating treaties related to the control of Nuclear Materials (NM) is the verification process, particularly when dealing with sensitive information. Normally, in this process, the inspector utilizes a suitable measuring system to verify the declared information. The difficulty may arise whenever sensitive information related to the NM should not be released to an inspector. Simultaneously, the NM owner (operator) should remain unaware of the measuring system employed by the inspector to prevent any probable manipulation. To address this issue, a neutral third party is assumed to act as an intermediary, who matches the data declared by the operator with the results obtained by the inspector, without exchanging any information between them. In this work, a Non-Intrusive System (NIS) is proposed and tested to play this role. The system receives data and information from both the operator and the inspector in the form of CAD or Monte Carlo (MC) input files, in addition to the results of measurements performed by the inspector. Then the system performs calculations and combines the results of these calculations with the inspector's measurement result to estimate the mass of the NM. The only information automatically conveyed to the inspector is the final conclusion regarding whether the declared and the estimated masses of NM are matched or not. The proposed NIS concept is tested using samples of NMs, and the results are presented.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105456"},"PeriodicalIF":3.3,"publicationDate":"2024-09-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142314722","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Understanding the effect of alkyl chain on extraction of Np4+ and Pu4+ with hexaalkyl nitrilotriacetamides into an ionic liquid vis-à-vis a molecular solvent","authors":"R.B. Gujar ,&nbsp;S.A. Ansari ,&nbsp;P.K. Mohapatra ,&nbsp;R.J.M. Egberink ,&nbsp;W. Verboom","doi":"10.1016/j.pnucene.2024.105455","DOIUrl":"10.1016/j.pnucene.2024.105455","url":null,"abstract":"<div><div>Extraction of actinides using exotic ligands in room temperature ionic liquids is one of the most preferred areas of research these days. Though the amides are well studied for the extraction of actinides from nitric acid feeds, multiple amides (such as tripodal amides) are of recent origin, and reports on solvent extraction with these ligands in room temperature ionic liquids are very rare. In this work, the extraction of Np⁴⁺ and Pu⁴⁺ was studied with a series of <em>N,N,N′,N′,N″,N″</em>-hexaalkyl nitrilotriacetamides (NTAamides) in an ionic liquid with an objective to understand the effect of the alkyl chains length on their extraction ability. Bumim⋅Tf₂N was chosen as ionic liquid due to its favourable viscosity for distribution studies. The extraction of tetravalent actinides Np⁴⁺ and Pu⁴⁺ increased linearly with increasing the alkyl chain of the NTAamides from <em>n</em>-butyl via <em>n</em>-hexyl to <em>n</em>-octyl. The extraction pattern was surprisingly opposite to the most observed extraction patterns in an ionic liquid, where the extraction generally decreases sharply upon increasing the feed acidity. The extracted species were ascertained as M(NO₃)₅⋅L (LH), where M = Np⁴⁺ or Pu⁴⁺, for each ligand. Consequent to the formation of an entirely divergent extracted complex, the extraction pattern is completely different than that expected in an ionic liquid.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105455"},"PeriodicalIF":3.3,"publicationDate":"2024-09-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142314723","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Optimization of pure elemental and oxide-based shielding materials for cost","authors":"Banks Peete,&nbsp;Stephen Trainor,&nbsp;Robert Hayes","doi":"10.1016/j.pnucene.2024.105444","DOIUrl":"10.1016/j.pnucene.2024.105444","url":null,"abstract":"<div><div>A common aspect to shielding material research is the combination of high atomic number inclusions with binders although the costs of the inclusions will vary with chemical form and have associated density and atomic number dependencies on attenuation properties. As most metals are cheaper in their oxide forms (sometimes drastically) we considered oxide forms to substantially reduce potential cost. This study then investigates the combined shielding and cost optimization of pure elemental and oxide-based shielding materials as well as steel, water and concrete. This focus on shielding effectiveness per cost and weight basis also incorporates contributions from scattered radiation in the form of radiation buildup for these comprehensive materials. In this sense, we define a new metric which incorporates cost, weight and scatter radiation for assessing shielding material attractiveness. We used MicroShield to calculate the shielding ability of each material. Our findings revealed that water, concrete, and lead demonstrated superior performance in terms of cost-effectiveness. This research contributes to the understanding of affordable and efficient shielding materials and has implications for industries reliant on radiation protection, such as nuclear power generation, medical imaging, and space exploration.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105444"},"PeriodicalIF":3.3,"publicationDate":"2024-09-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142314725","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}