Nuclear Engineering International最新文献_第5页

Bethsy Test 6.9C Mid-Loop Operation Phenomena Identification Using RELAP5 NPA 利用RELAP5 NPA识别Bethsy Test 6.9C中回路运行现象

IF 0.6 4区工程技术

Nuclear Engineering International Pub Date : 1997-11-16 DOI: 10.1115/imece1997-0605

S. Petelin, B. Mavko, M. Jurković

引用次数: 0

Bubbly Flow Identification Using Particle Image Velocimetry 用粒子图像测速法识别气泡流

IF 0.6 4区工程技术

Nuclear Engineering International Pub Date : 1997-11-16 DOI: 10.1115/imece1997-0606

Y. Hassan, W. Schmidl, J. Ortíz-Villafuerte

引用次数: 0

Data Transfer From BETHSY 9.1B Experiment to Real NPP 从BETHSY 9.1B实验到实际NPP的数据传输

IF 0.6 4区工程技术

Nuclear Engineering International Pub Date : 1997-11-16 DOI: 10.1115/imece1997-0609

S. Petelin, B. Mavko, I. Ravnikar, Y. Hassan

引用次数: 2

Features of the Calculational Method at Fluid Flow Modelling 流体流动模型计算方法的特点

IF 0.6 4区工程技术

Nuclear Engineering International Pub Date : 1997-11-16 DOI: 10.1115/imece1997-0604

G. Černe, S. Petelin

引用次数: 0

Computational Fluid Dynamics Analysis of Thermal Mixing in the AP600 Upper Head AP600上封头热混合计算流体力学分析

IF 0.6 4区工程技术

Nuclear Engineering International Pub Date : 1997-11-16 DOI: 10.1115/imece1997-0608

R. Schwirian

引用次数: 0

Application of the WCOBRA/TRAC Best Estimate Methodology to the AP600 Large-Break LOCA Analysis WCOBRA/TRAC最佳估计方法在AP600大断裂LOCA分析中的应用

IF 0.6 4区工程技术

Nuclear Engineering International Pub Date : 1997-11-16 DOI: 10.1115/imece1997-0603

Jinzhao Zhang, S. Bajorek, R. M. Kemper, M. Nissley, N. Petkov, L. Hochreiter

{"title":"Application of the WCOBRA/TRAC Best Estimate Methodology to the AP600 Large-Break LOCA Analysis","authors":"Jinzhao Zhang, S. Bajorek, R. M. Kemper, M. Nissley, N. Petkov, L. Hochreiter","doi":"10.1115/imece1997-0603","DOIUrl":"https://doi.org/10.1115/imece1997-0603","url":null,"abstract":"\u0000 The AP600 is a simplified advanced pressurized water reactor (PWR) design incorporating passive safety systems that perform the same function as the active emergency core cooling systems (ECCSs) on the current reactors. In order to verify the effectiveness of the AP600 design features for mitigation of a postulated large-break loss-of-coolant accident (LOCA), the recently USNRC-approved best-estimate LOCA methodology (BELOCA) was applied to perform the AP600 standard safety analysis report large-break LOCA analysis. The applicability of the WCOBRA/TRAC code to model the AP600 unique features was validated against CCTF and UFTE downcomer injection tests, the blowdown and reflood cooling heat transfer uncertainties were re-assessed for the AP600 large-break LOCA conditions, and a conservative minimum film boiling temperature was applied as a bounded parameter for blowdown cooling. The BELOCA methodology was simplified to quantify the code uncertainties due to local and global models as well as the statistical approximation methods, with the other uncertainties being bounded by limiting assumptions on the initial and boundary conditions. The final 95 percentile peak cladding temperature (PCT95%) was 1186 K, which meets the 10CFR50.46 criteria with a considerable margin. It is therefore concluded that the AP600 design is effective in mitigation of a postulated large-break LOCA.","PeriodicalId":49736,"journal":{"name":"Nuclear Engineering International","volume":"49 1","pages":""},"PeriodicalIF":0.6,"publicationDate":"1997-11-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"78860045","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

Scaling Analysis of AP600 Long Term Cooling Performance AP600长期冷却性能的结垢分析

IF 0.6 4区工程技术

Nuclear Engineering International Pub Date : 1997-11-16 DOI: 10.1115/imece1997-0611

M. G. Ortiz, Constance E. Nielson, Laura Teerlink

{"title":"Scaling Analysis of AP600 Long Term Cooling Performance","authors":"M. G. Ortiz, Constance E. Nielson, Laura Teerlink","doi":"10.1115/imece1997-0611","DOIUrl":"https://doi.org/10.1115/imece1997-0611","url":null,"abstract":"\u0000 Westinghouse’s AP600 thermohydraulic design, with passive safety features, poses new challenges to computer simulation and analyses, the design of experimental test facilities to represent it, and to the proper interpretation of the data from these facilities. The conventional approach of modeling the reactor thermohydraulic system as a closed, steady state, natural circulation loop from which non-dimensional groups of parameters can be derived and used in the design of integral tests, is limited and can not capture the abrupt time-varying open system nature of the new design.\u0000 A rigorous and systematic, eight-step methodology has been developed to scale and interpret the results from three different integral test facilities, and to relate them to the full scale plant. In this paper, the aforementioned scaling methodology is applied to the analysis of the long term cooling phase of the AP600 behavior. This long term cooling phase, which appears independent of the initiating event, is divided for its analysis into two sub-phases. A first sub-phase dominated by the draining of the large In-Containment Refueling Water Storage Tank through the primary systems, and a second sub-phase characterized by the quasi-steady recirculation of coolant through the reactor vessel and the outside of the primary system. The analysis shows that with a few verifiable assumptions one can determine the key parameters and non-dimensional groups that govern the behavior in either of these sub-phases. One then uses these parameters and non-dimensional groups to evaluate the relevancy of existing test data.","PeriodicalId":49736,"journal":{"name":"Nuclear Engineering International","volume":"1 1","pages":""},"PeriodicalIF":0.6,"publicationDate":"1997-11-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83989612","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

Heat Transfer in Laminar Channel Flow With a Non-Uniform Porous Media 非均匀多孔介质层流通道的传热研究

IF 0.6 4区工程技术

Nuclear Engineering International Pub Date : 1997-11-16 DOI: 10.1115/imece1997-0615

X. Huang, W. Qin, C. Y. Liu, K. Toh

{"title":"Heat Transfer in Laminar Channel Flow With a Non-Uniform Porous Media","authors":"X. Huang, W. Qin, C. Y. Liu, K. Toh","doi":"10.1115/imece1997-0615","DOIUrl":"https://doi.org/10.1115/imece1997-0615","url":null,"abstract":"\u0000 This paper presents a numerical study on heat transfer by laminar flows in a two-dimensional channel. The channel is filled with a porous material which is assumed to be non-uniform across the channel, especially near the channel walls where the permeability of the porous material increases drastically to simulate the complexity at the interface between the porous media and the solid walls. Degrees of the non-uniformity of the porous material are described in this study by a parameter β. Heat sources, either constant temperature or constant heat flux, are located on the channel walls, so that heat transfer from the sources into the channel flow is greatly affected by the condition at the wall-porous media interfaces. The temperature distribution near the heat source region and the Nusselt numbers are calculated for different β values. The sensitivity of the non-uniformity of the porous media near the channel walls on the overall heat transfer is assessed. It is found that a higher non-uniformity of the porous material near the channel wall can actually enhance the heat transfer from the sources to the channel flow, as the flow velocity near the wall has been significantly increased due to the higher permeability of the porous material in the near-wall region.","PeriodicalId":49736,"journal":{"name":"Nuclear Engineering International","volume":"9 1","pages":""},"PeriodicalIF":0.6,"publicationDate":"1997-11-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84235520","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

CFD Analysis of Thermal Mixing and Stratification in AP600 Auxiliary Lines AP600辅助管线热混合分层的CFD分析

IF 0.6 4区工程技术

Nuclear Engineering International Pub Date : 1997-11-16 DOI: 10.1115/imece1997-0614

A. Harkness, R. Schwirian, P. Dymáček

引用次数: 0

Heat Transfer Modeling of the LSTF Passive Residual Heat Removal System LSTF被动余热去除系统的传热建模

IF 0.6 4区工程技术

Nuclear Engineering International Pub Date : 1997-11-16 DOI: 10.1115/imece1997-0612

G. McCreery, C. Kullberg, R. Schultz, T. Yonomoto, Y. Anoda

引用次数: 0