Progress in Nuclear Energy最新文献_第6页

Gamma radiation induced tailoring the structural, optical, surface and mechanical properties of UHMWPE 伽马辐射诱导定制超高分子量聚乙烯的结构、光学、表面和机械性能

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2024-10-08 DOI: 10.1016/j.pnucene.2024.105481

Sultan J. Alsufyani , M.F. Zaki , T.S. Soliman , Nadi Mlihan Alresheedi , Tayseer I. Al-Naggar

{"title":"Gamma radiation induced tailoring the structural, optical, surface and mechanical properties of UHMWPE","authors":"Sultan J. Alsufyani , M.F. Zaki , T.S. Soliman , Nadi Mlihan Alresheedi , Tayseer I. Al-Naggar","doi":"10.1016/j.pnucene.2024.105481","DOIUrl":"10.1016/j.pnucene.2024.105481","url":null,"abstract":"<div><div>The present investigation examined how the resultant gamma radiation affected the ultra-high molecular weight polyethylene's (UHMWPE) mechanical, optical, surface, and structural characteristics. Different gamma doses of 75, 150, 250, and 350 kGy were applied to the UHMWPE samples. The study of physical and chemical qualities has involved a variety of spectroscopy techniques, including Fourier Transform Infrared spectroscopy, X-ray diffraction, mechanical property changes, and biocompatibility properties. New bands are formed, as indicated by FT-IR analysis, and this process is linked to the oxidation of irradiation polymer chains and the production of carbon dioxide. The crystallinity of irradiated samples increases as the gamma radiation increases, according to XRD patterns. The analyzed optical results exhibit improvements in the optical characteristics of the irradiated samples. The absorbance spectra of the irradiated samples showed a shift toward the high of wavelength values in the absorption edge as compared to the pristine sample. On the other hand, the optical absorption edge has an increasing tendency as the dose of gamma-ray radiation is increased. As the gamma-ray dose increases, the absorption edge moves toward the longer wavelength. The measurements of the contact angle indicate that the surface free energy rises with increasing gamma irradiation. It was detailed how the mechanical properties of the irradiated UHMWPE samples were measured. The mechanical measurements indicate that the mechanical properties are dose-dependent to some extent. Furthermore, as gamma doses rise, so does the hardness of irradiated UHMWPE.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105481"},"PeriodicalIF":3.3,"publicationDate":"2024-10-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142423747","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}

引用次数: 0

A subchannel analysis code for advanced liquid metal fast reactor cores and study on heat transfer characteristics of core geometry parameters 先进液态金属快堆堆芯子通道分析代码及堆芯几何参数传热特性研究

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2024-10-07 DOI: 10.1016/j.pnucene.2024.105477

Bin Han , Yuanyuan Yin , Xiaoliang Zhu , Bao-Wen Yang , Shenghui Liu , Lingping Song , Aiguo Liu , Tianyang Xing

{"title":"A subchannel analysis code for advanced liquid metal fast reactor cores and study on heat transfer characteristics of core geometry parameters","authors":"Bin Han , Yuanyuan Yin , Xiaoliang Zhu , Bao-Wen Yang , Shenghui Liu , Lingping Song , Aiguo Liu , Tianyang Xing","doi":"10.1016/j.pnucene.2024.105477","DOIUrl":"10.1016/j.pnucene.2024.105477","url":null,"abstract":"<div><div>The liquid metal fast reactor represents an important reactor type for the future development of nuclear energy. Accurately modeling and predicting the subchannel flow and heat transfer phenomenon in the rod bundles plays a key role in ensuring core safety. Consequently, a subchannel code suitable for the liquid metal fast reactor is analyzed based on the subchannel analysis code of the Pressurized Water Reactor (PWR). The modified code incorporates various types of liquid metals, such as lead, lead-bismuth eutectic (LBE), and sodium, along with their constitutive models, enhancing the applicability of the liquid metal reactor systems. This code has been verified and validated at several levels, including comparing the code simulation results with other similar subchannel codes results, high-dimensional Computational Fluid Dynamics (CFD) simulations, and experiment data. The sensitivity analysis of core geometric parameters and turbulent mixing coefficients is performed based on the modified version code. The influence of the core geometry, including the rod Pitch to Diameter ratio (P/D), Rod to Wall gap (RTW) and the wire wrap pitch (H) on the sensitivity of outlet temperature has been investigated. The results show that the new subchannel analysis code suitable for liquid metal cooled reactor shows reasonable agreement with the verified and validated results. The geometric parameters, such as P/D, RTW and H have noticeable effects on the outlet temperature difference of the subchannels. Additionally, the outlet temperature distribution in the subchannel is significantly affected by different turbulent mixing coefficients and the distribution of the turbulent mixing coefficient also influenced by the reactor core sizes. Overall, this study could support the rod bundles design and safety analysis in the liquid metal reactors.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105477"},"PeriodicalIF":3.3,"publicationDate":"2024-10-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142423742","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}

引用次数: 0

A review on methods and applications of artificial intelligence on Fault Detection and Diagnosis in nuclear power plants 人工智能在核电站故障检测和诊断中的方法和应用综述

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2024-10-05 DOI: 10.1016/j.pnucene.2024.105474

Aicheng Gong , Zhongjian Qiao , Xihui Li , Jiafei Lyu , Xiu Li

{"title":"A review on methods and applications of artificial intelligence on Fault Detection and Diagnosis in nuclear power plants","authors":"Aicheng Gong , Zhongjian Qiao , Xihui Li , Jiafei Lyu , Xiu Li","doi":"10.1016/j.pnucene.2024.105474","DOIUrl":"10.1016/j.pnucene.2024.105474","url":null,"abstract":"<div><div>Nuclear power plants are critical facilities, which can generate a lot of energy through nuclear power and reduce environmental pollution. At the same time, should an accident occur at nuclear power plants, such as a nuclear leak, the consequences can be more severe than those associated with traditional power generation facilities. Therefore, Fault Detection and Diagnosis (FDD) has been an important technology in nuclear power plants. Traditional FDD methods mostly rely on the precise mathematical system model, which can be sometimes difficult to obtain in reality, and the detection accuracy of existing methods is thus limited. With the development of artificial intelligence (AI) technologies, FDD methods based on AI have been widely used. In this work, we make a systematic review of AI-based FDD methods, in conjunction with the introduction of the traditional FDD methods, and present the corresponding application scenarios of them. We hope that this work will help researchers incorporate more advanced AI models in nuclear power plants FDD and enlighten those interested in this field.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105474"},"PeriodicalIF":3.3,"publicationDate":"2024-10-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142423282","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}

引用次数: 0

Design of experimental facility for helium gas component testing 设计氦气组件测试实验设施

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2024-10-05 DOI: 10.1016/j.pnucene.2024.105471

Silvino A. Balderrama Prieto , Zachary D. Sellers , David Arcilesi , Piyush Sabharwall

引用次数: 0

The sampling and removal of tritiated water vapor in Taiwan research reactor 台湾研究反应堆中三价水蒸气的取样和去除

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2024-10-05 DOI: 10.1016/j.pnucene.2024.105482

Jhih-Jhong Huang, Peng-Yu Chen

{"title":"The sampling and removal of tritiated water vapor in Taiwan research reactor","authors":"Jhih-Jhong Huang, Peng-Yu Chen","doi":"10.1016/j.pnucene.2024.105482","DOIUrl":"10.1016/j.pnucene.2024.105482","url":null,"abstract":"<div><div>The Taiwan Research Reactor (TRR) is a research facility in Taiwan. TRR is a heavy water reactor designed based on the National Research Experiment (NRX) with output thermal power 40 MW. On January 3, 1973, it reach criticality. TRR had been operated for 15 years and was permanently shut down in early 1988. TRR uses heavy water moderation and light water cooling. Hence, some tritium was created when deuterium captures a neutron. The inside of the Calandria has been washed with clean water after shutdown. After draining the water in the interior, it is inevitable that some residual water would remain at the bottom of the Calandria. Air sampling and analysis techniques were employed to detect and quantify tritiated water vapor. The investigation of tritiated water vapor in the TRR Calandria proved potential tritium contamination risks. Adopting the vapor condensation drying technique proved effective in removing tritiated water vapor from the TRR Calandria. After the removal of tritiated water vapor, the air in the Calandria no longer contains rich concentration of tritiated water vapor. That will help to ensure a safe environment for decommissioning operations.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105482"},"PeriodicalIF":3.3,"publicationDate":"2024-10-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142423744","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}

引用次数: 0

Aloe barbadensis - Assisted MgBiO/MgCuBiO/MgBaBiO nanocomposites as effective gamma shielding novel materials 芦荟--辅助镁硼氧化物/镁铜硼氧化物/镁钡硼氧化物纳米复合材料作为有效的伽马屏蔽新型材料

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2024-10-04 DOI: 10.1016/j.pnucene.2024.105470

K. Kruthika , S.M. Rumana Farheen , H.C. Manjunatha , Y.S. Vidya , S. Manjunatha , R. Munirathnam , S. Krishnaveni , K.N. Sridhar

{"title":"Aloe barbadensis - Assisted MgBiO/MgCuBiO/MgBaBiO nanocomposites as effective gamma shielding novel materials","authors":"K. Kruthika , S.M. Rumana Farheen , H.C. Manjunatha , Y.S. Vidya , S. Manjunatha , R. Munirathnam , S. Krishnaveni , K.N. Sridhar","doi":"10.1016/j.pnucene.2024.105470","DOIUrl":"10.1016/j.pnucene.2024.105470","url":null,"abstract":"<div><div>For the first of its kind, MgO/Bi<sub>2</sub>O<sub>3</sub> (1:1) (MBO), MgO/CuO/Bi<sub>2</sub>O<sub>3</sub> (1:1:1) (MCBO) and MgO/BaO/Bi<sub>2</sub>O<sub>3</sub> (1:1:1) (MBBO) binary/ternary nanocomposites (NCs) were synthesized by Aloe barbadensis (Aloe vera) mediated solution combustion method. The as-formed NCs are subjected to calcination for 3 h at 600<sup>o</sup>C.The Mg-based NCs acquired are subjected to various analytical characterization methodologies, including PXRD (Powder X-ray Diffraction), SEM (Scanning Electron Microscopy), EDS (Energy Dispersive X-ray Spectroscopy), FTIR (Fourier Transform Infrared Spectroscopy), and Ultraviolet–Visible Spectroscopy (UV–Vis). The Bragg reflections confirm the formation of monoclinic phase BaO, Bi<sub>2</sub>O<sub>3</sub>, cubic MgO and tetragonal CuO nanoparticles. The surface morphology of MBO, MCBO and MBBO NCs consists of irregular sized, leafy and burrow like structured agglomerated NPs with hollows and voids/pores. The Eg (direct energy band gap) determined from W-H (Wood and Tauc's) plot was found to be 3.09, 3.19 and 3.12 eV for MBO, MCBO and MBBO NCs respectively. The evaluation of gamma radiation shielding properties was conducted using a NaI (Tl) detector connected to a multi-channel analyzer. Shielding parameters of MBO, MCBO and MBBO, such as μ/ρ (mass attenuation coefficient), λ (mean free path), HVL (half-value layer), TVL (tenth-value layer) are measured. Among the as-synthesized Mg-based NCs, MBO exhibits better shielding properties compared to MCBO and MBBO. Thus, the procured Mg-based NCs are suitable for applications where weight reduction is critical, such as aerospace or portable radiation shielding systems.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105470"},"PeriodicalIF":3.3,"publicationDate":"2024-10-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142423752","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}

引用次数: 0

Study on the effect of Lorentz force on the nuclear reactor core melt stratification in electromagnetic cold crucible 洛伦兹力对电磁冷坩埚中核反应堆堆芯熔体分层的影响研究

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2024-10-03 DOI: 10.1016/j.pnucene.2024.105475

Kerong Guo , Yang Li , Houjun Gong , Yuanfeng Zan , Zumao Yang , Yanping Huang

{"title":"Study on the effect of Lorentz force on the nuclear reactor core melt stratification in electromagnetic cold crucible","authors":"Kerong Guo , Yang Li , Houjun Gong , Yuanfeng Zan , Zumao Yang , Yanping Huang","doi":"10.1016/j.pnucene.2024.105475","DOIUrl":"10.1016/j.pnucene.2024.105475","url":null,"abstract":"<div><div>To understand the effect of the Lorentz force on core melt stratification during experiments, a multi-physical field coupling model of electromagnetic induction, non-isothermal flow, and two-phase flow is established in this paper. The evolution of the layered core melt in the electromagnetic cold crucible is studied for different relative densities and phase volume fraction ratios between metal and oxide. The calculation results show that the coupling model can accurately describe the structural evolution of core melt. The Lorentz force cannot change the relative positions of the metal and oxide, but it can significantly affect the morphology of the core melt. If the density of the metal is less than that of the oxide, the Lorentz force causes the light metal with a small phase volume fraction to form a hemispherical shape in the top center of the crucible. As the phase volume fraction increases, the Lorentz force become weaker than those of gravity and buoyancy. The light metal is then flat. When the metal density is greater than the oxide density, the Lorentz force causes the heavy metal with a small phase volume fraction to appear as a hemisphere, but causes the heavy metal with a large phase volume fraction to appear as an ellipsoid in the lower part of the crucible.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105475"},"PeriodicalIF":3.3,"publicationDate":"2024-10-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142423739","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}

引用次数: 0

Improvement and validation of discrete-sectional method based code for fast reactor aerosol dynamics 基于离散截面法的快堆气溶胶动力学代码的改进与验证

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2024-10-03 DOI: 10.1016/j.pnucene.2024.105457

Shikha Sivakumar, A Jasmin Sudha, V. Subramanian, B. Venkatraman

{"title":"Improvement and validation of discrete-sectional method based code for fast reactor aerosol dynamics","authors":"Shikha Sivakumar, A Jasmin Sudha, V. Subramanian, B. Venkatraman","doi":"10.1016/j.pnucene.2024.105457","DOIUrl":"10.1016/j.pnucene.2024.105457","url":null,"abstract":"<div><div>The study of the dynamics of aerosols produced during a severe accident is vital to the safety analysis of a Sodium-cooled Fast Reactor (SFR). Sodium leakage into the containment following a severe accident may result in the production of sodium aerosols along with fission product aerosols. The in-containment radioactive source term depends upon the settling behaviour of fission product aerosols, which co-agglomerate with sodium fire aerosols. Hence, an in-depth understanding of the dynamics and deposition of aerosols within the containment is essential for the safety assessment of an SFR. The current work uses an open-source code based on the Discrete-Sectional (DS) method to solve the simplified form of General Dynamics Equation (GDE) for aerosols relevant to fast reactors. Aerosols of SrO<sub>2</sub>, CeO<sub>2</sub> and sodium are considered in the present work. The DS code has been modified and further improved by including gravitational coagulation, turbulent coagulation, Brownian deposition, gravitational deposition and thermophoretic deposition so that the code can handle the different processes leading to the deposition of aerosols following a sodium fire. The code is also enhanced to account for the effect of relative humidity through the modified Cooper's equation. The improved code is then validated with different experiments conducted in the Aerosol Test Facility (ATF), India; Mini Sodium Fire Facility (MINA), India; and AHMED (Aerosol and Heat Transfer Measurement Device), Finland. Validation from different facilities confirms the applicability of the code to various scenarios. It is found that the modified DS code could predict the decay of suspended mass concentration of aerosols in different enclosures with reasonable accuracy.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105457"},"PeriodicalIF":3.3,"publicationDate":"2024-10-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142423741","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}

引用次数: 0

A neutronics-fuel coupling model for the simulation of constituent redistribution in U–Zr fuel 用于模拟 U-Zr 燃料中成分再分布的中子-燃料耦合模型

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2024-10-03 DOI: 10.1016/j.pnucene.2024.105467

Oscar Lastres, Yunlin Xu, Yi Xie

{"title":"A neutronics-fuel coupling model for the simulation of constituent redistribution in U–Zr fuel","authors":"Oscar Lastres, Yunlin Xu, Yi Xie","doi":"10.1016/j.pnucene.2024.105467","DOIUrl":"10.1016/j.pnucene.2024.105467","url":null,"abstract":"<div><div>Simulating the dynamic redistribution of elements within metallic fuels, such as U–10Zr (wt.%), is a complex challenge in nuclear power research. While existing models can adequately simulate constituent redistribution throughout the fuel pin, they rely heavily on pre-known power history data or power calculated <em>a priori</em>. Furthermore, existing models do not calculate an accurate actinide inventory throughout the fuel pin. This limitation leads to less precise power distribution calculations, which can negatively affect the efficiency and safety of fuel design and performance. This work aims to introduce a new approach to modeling constituent redistribution for U–10Zr (wt.%) fuel by developing a new code called PFPS that accounts for the depletion and diffusion of Zr throughout the fuel pin during burnup through an explicit coupling method. The approach independently calculates the power distribution by coupling with the reactor physics code, Serpent 2, thereby eliminating the need for externally supplied power history data. The main contribution of this study lies in this coupling to obtain a more accurate history of the compositional evolution of U–Zr fuel and its fission products. This procedure can enhance the understanding of constituent redistribution by calculating a more accurate power distribution and lays the foundation for future attempts to simulate the compositional and microstructural evolution of all materials in the fuel.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105467"},"PeriodicalIF":3.3,"publicationDate":"2024-10-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142423740","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}

引用次数: 0

Main lessons learnt from 40 years of R&D on iodine source term prediction: Identification of the main parameters governing iodine volatility in PHEBUS FP tests 从 40 年的碘源期预测研发中汲取的主要经验教训：确定 PHEBUS FP 试验中影响碘挥发的主要参数

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2024-10-03 DOI: 10.1016/j.pnucene.2024.105473

Loïc Bosland, Karine Chevalier-Jabet

{"title":"Main lessons learnt from 40 years of R&D on iodine source term prediction: Identification of the main parameters governing iodine volatility in PHEBUS FP tests","authors":"Loïc Bosland, Karine Chevalier-Jabet","doi":"10.1016/j.pnucene.2024.105473","DOIUrl":"10.1016/j.pnucene.2024.105473","url":null,"abstract":"<div><div>Iodine chemistry and phenomenology in the containment has been studied for several decades. The main phenomena leading to the formation of volatile iodine have been identified step by step and their kinetics has been modeled and capitalized over the years in ASTEC-SOPHAEROS IRSN Severe Accident (S.A) code. Recently, the uncertainties for each phenomenon have been quantified and uncertainty propagation calculations have been performed on PHEBUS FPT-0/1/2/3 tests within the objective to identify which phenomena govern iodine volatility. The main highlights from PHEBUS studies are that (1) the sump reactions do not contribute to iodine volatility and (2) the gaseous phase chemical reactions are the main contributor to iodine volatility and (3) only a few gaseous reactions govern iodine volatility in PHEBUS containment. Another objective was to narrow the estimated range of %I<sub>2_RCS</sub> (gaseous iodine fraction coming from the RCS). The results show that, considering 43 uncertain parameters, the iodine volatility plume is compatible with the experimental data whatever 2% < %I<sub>2_RCS</sub> < 50% that mostly govern iodine volatility in the first days. It also indicates that, as soon as the FP release from the core is stopped and whatever 2% < %I<sub>2_RCS</sub> < 50%, the influence of %I<sub>2_RCS</sub> decreases over time so that the main processes leading to iodine volatility are slowly switched from %I<sub>2_RCS</sub> (short term) to other gaseous phenomena (long term). The influence of %I<sub>2_RCS</sub> on iodine volatility is thus important in the short term but becomes less and less significant in the long term (after several days). A more complete analysis is necessary for reactor applications to identify if the same conclusions can be drawn.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105473"},"PeriodicalIF":3.3,"publicationDate":"2024-10-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142423281","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}

引用次数: 0