姜胜耀
长期从事反应堆热工水力学及两相流动不稳定性研究。
个性化签名
- 姓名:姜胜耀
- 目前身份:
- 担任导师情况:
- 学位:
-
学术头衔:
博士生导师
- 职称:-
-
学科领域:
能源科学技术
- 研究兴趣:长期从事反应堆热工水力学及两相流动不稳定性研究。
姜胜耀,男,1959 年10 月生,吉林长春人,教授,博士生导师。1984 年清华大学本科毕业,1986 年清华大学硕士毕业,1991—1995 年赴德国斯图加特大学获博士学位,师从世界著名反应堆专家D . Emendoefer 及世界著名热工专家E . Hahne 教授,博士论文作为德国正式出版物发表。现任国家十五“863 ”计划后续能源主题管理专家、主题专家委员会成员,教育部“先进反应堆工程与安全”重点实验室主任,清华大学责任教授,核能科学与工程研究所副所长,清华大学“核科学与技术”学位分委员会委员,日本原子能研究院特聘访问教授,“原子能科学技术”杂志编辑委会委员,“Nuc1ear Engineering and Design”的编委,教育部“核科学与技术”网上合作研究中心副主任。获国家杰出青年科学基金,自然科学基金,教育部跨世纪人才基金,国家985 、973 及国际合作研究等项目支持。长期从事反应堆热工水力学及两相流动不稳定性研究,提出自然循环流量漂移,闪蒸不稳定,闪蒸耦合密度波不稳定,喷泉诱发闪蒸不稳定等多种新的两相流不稳定性现象,发表论文110 篇,被SCI 、EI 收录70 余篇,研究成果获国际大会优秀论文奖1 项,获国家、部委级奖励9 项。
-
主页访问
7038
-
关注数
0
-
成果阅读
774
-
成果数
10
【期刊论文】Experimental Study of Two-Phase Flow Oscillation in Natural Circulation
姜胜耀, S.Y. Jiang, *, X.X. Wu, and Y.J. Zhang
NUCLEAR SCIENCE AND ENGINEERING: 135, 177-198 (2000),-0001,():
-1年11月30日
The experiment was performed on the test loop HRTL-5, which simulates the geometry and system design of the 5-MW nuclear heating reactor developed by the Institute of Nuclear Energy Technol-ogy, Tsinghua University. The flow behovior for a wied range of ilet subcoolings, in which the flow ex-perience varies from single-to two-phase, is described in a natural circulation system at different pressures (P=0.1, 0.24, and 1.5 Mpa). Several kinds of flow instability are investigated, including geysering, flashing-related flow instability. And high-frequency flow oscillation at P=0.1 and 0.24Mpa, as well as low steam quality density wave oscillation at P=1.5Mpa. The mechanisms of geysering, which has new features, and flashing-related flow instability. Which has never been studied well enough in this field, are particu-larly interpreted. The experimental results show the following: First. For a low-pressure natural circula-non system. The two-phase flow is unstable in most inlet subcooling conditions, and the two-phase stable flow can be reached only with very low inet subcoolings. Second, at high inlet subcoolings, the flow instability is dominated by subcooling boiling in the heated section, and at intermediate inlet subcoolings, it is dominated by void flashing in the adiabatic long riser. Third. In the two-phase stable flow region, the conditions for boiling out of the core. Namely. Single-phase flow in the heated section and two-phase flow in the riser due to vapor flashing, can be realized. The experimental results are of significance for the degign and accident analysis of vessel and swimming pool-type natural circulation nuclear hearting reactors.
-
71浏览
-
0点赞
-
0收藏
-
0分享
-
105下载
-
0评论
-
引用
姜胜耀, S.Y. Jiang, X.T. Yang and Y.J. Zhang
,-0001,():
-1年11月30日
The two-phase flow is a kind of dissipative structure in multiphase hydrodynamics. A drift-flux model with four equations is adopted to investigate the natural circulation bifurcation, in which the sub-cooled boiling, condensation, and void fraction etc. have been taken into occount. The bifurcation spectrum of a natural circulation system with low steam quality and low system pressure is presented and the physical mechanisms of bifurcation are described in detail. Bifurcation characteristics of the two-phase natural circulation indicate typical static instability observed in HRTL-5 simulating the geometry and system design of the 5MW nuclear heating reactor operating at low steam quality and low system pressure. Analysis shows: (1) bifurcation phemomenon can occur in a two-phase natural circulation under certain thermal and geometrical condition; (2) with changing, namely increasing and decreasing, control parameters, the tracks of the work points of the natural circulation system are not identical, which shows the basic characteristic of the bifurcation phemomenon; (3) the bifurcation phenomenon of the natural circulation delay and disappear with increasing system pressure and decreasing heat flux.
-
78浏览
-
0点赞
-
0收藏
-
0分享
-
97下载
-
0评论
-
引用
姜胜耀, X. Yang, s.y. Jiang and Y. Zhang
,-0001,():
-1年11月30日
This Paper describes expedmenm|and numerical investrga. tlons of sub-cooled boiling, condensadon, and void flashing in the HRTL-5 test loop, which simulates the primary loop of a 5 MW nuclear heating reactor. A drift-flow model of two-phase with four govenffng equations was used, in which sub-cooled boiling, eondensalion nnd void flashing hove been taken into account. Based on the mathemadcal model, a program has been developed for analyzing the namral cir-culation system. As parameters, inlet sub-cooling, system pres-sure, and heat flux are varied. For comparison, some simpli-fied modeis, which are designed to reveal the importance of sub-cooled boding, condensation, flashlog in the HRTL-5 test loop. are adopted in the program. The results show: (1) sub-cooled boiling. condensatian, and void flashing may have great influence on the distributlon oF the void fracdon and morP intense at low system pressure; (2) the calculaiion of them is correlatire and interactive other than independent; (3) for a system with short heated sealon. long riser, and low pressure, it is possible to reach "boiling out of the core", where is almosl no void in the heated seelion bul much in the riser.
-
90浏览
-
0点赞
-
0收藏
-
0分享
-
112下载
-
0评论
-
引用
【期刊论文】Thermal hydraulic modeling of a natural circulation loop*
姜胜耀, S.Y. Jiang, X.X. Wu, Y.J. Zhang, H.J. Jia
Heat and Mass Transit 37 (2001) 387-395,-0001,():
-1年11月30日
The experiment was carried out on fhe test loop HRTL-5, which simulates the geometry and system design of a 5 MW nuclear heating reactor The analysiswasbased on a one-dimensfonal two-phase flow drift model with conservation equations for mass, steam, energy and mo-mentum. Clausius-Clapeyron equation was used for the calculation offlashing front in the riser. A set ofordinary eguations, which describes the behavior oftwo phase flow in the natural circulation system. was derived through Integrafion of the above conservation equations for the subcooled boiling region, bulk boiling region in the heated section and for the riser. The method of time-domain was used for the talc uIation Both static and dynamic results are presented System pressure, inlet subcooling and heat flux are varied as input parameters. The results show that subcooled boiling in the heated section and void flashing In the riser have significant jnfluence oN the distribution of the void fraction, mass flow rate and flow instability ofthe system, especially at low pressure The response of nlass flow rate. after a small disturbance in the heat flux is shown, and based on it the instability map ofthe system is given through experiment and calculation. There exists three regions in the instability map of the investigated natural circulation system, namely, the stable two-phase flow region, the unstable bulk and subcooled boiling flow region and the stable subcooled boiling and single phase flow region. The mechanism of two-phase flow osciHation is interpreted.
-
80浏览
-
0点赞
-
0收藏
-
0分享
-
96下载
-
0评论
-
引用
【期刊论文】Flow excursion phenomenon in natural circulation at nuclear heating reactor conditions
姜胜耀, S.Y. Jiang, Y.J. Zhang, X.X. Wu, J.H. Bo and H.J. Jias. Y. Jiang, J.H. Bo and H.J. Jia
,-0001,():
-1年11月30日
The etperiment Was performed pn the test loop (HRTL-5). which sinmlates the geometry and system design of a 5MW nuclear beating rcator In a Wide range of inlel subcoolings different flow features. such as single phase stable flow, sub-Cooled boiling stable flow, subcooled boiling staticpow excur-sion, density wave oscillalion and stable two phase flow in the mlnlral circulalion Svstem have been described The pheno menon and mecchanisnt of static flow excursion. which has never been smdied well in this field is especialIv interpreted. The erperimental results show that static flow excursion exists under certain inlet sttbcooling condilion in which only sub-COOled boiling occurs in the heated section In the process of flow excursion the mass flow rate and the inlef temperanlre decreases. while the exit temperature increases smoothly. As tbe process of excursion contimles for about 1 hour, bubbles enter in the flow. channel resulling in shorl period dynamic flow oscillalion which can only be seen in the process of this static flow excursion and has also never be studied well. These static arid dynamic flo instabilities combine ror about 2 hour. Then a point iS reached. at which the stalic, flow excursion stops, but the dynamic flow oscillation continues. The Study of flow excursion ond its concerned dynamic flow oscillation is of great significance for the delelopment of muclear heating reactor under natural circubttion.
-
97浏览
-
0点赞
-
0收藏
-
0分享
-
81下载
-
0评论
-
引用
姜胜耀, S.Y.X. Jiang, X. Yang and Y. Zhang
,-0001,():
-1年11月30日
This paper describes computational and experimental investi-gations of statioc characteristics of a natural circulation system at nuclear heating reactor onditions. Characteristic curves of a natureal circulation system hae been obtatined by using a and flashing have been taken into account. Using characteristic curves to analyze the behavior of the natural circulation is a new method.As an example, flow excursion and heat siphon in a natural circulation with low steam quality and low pres-sure have been describe by means of using the method of characteristic curves. The results show, that, under certain con-ditions, flow excurves. The resuts show, that, under certain con-ditions, flow excursion wil occur in a natural circulation sys-tem. The value predicted by the computing model is very close to the experimental value.
-
109浏览
-
0点赞
-
0收藏
-
0分享
-
36下载
-
0评论
-
引用
姜胜耀, S.Y. Jiang*, L.L. Gao, Y.J. Zhang, J.H. Bo
Annals ofNuclear Energy 28 (2001) 251-263,-0001,():
-1年11月30日
The gravity-driven boron injection system (GDBIS), designed by the Institute of Nuclear Energy Technology (INET) of the Tsinghua University, PR China, is a new type of passive system to be applied in the 200 MW nuclear heating reactor (NHR-200), also designed by INET The function of this system iS to shut down the reactor in a13 emergency. in case con-trol rods do not operate properly. A borate water tank is 10 cated 10m above the top of the pressure vessel When the pressure of the reactor and the boron tank balances, the borate water will be driven by gravity to flow Into the reactor. and thus shut down the reactor The thermal hydraulic perforrnances of the system for cold froom temperature nitrogenl and hot (mixture of hot steam and nitrogen) operating conditions, especially the response time of pressure and water injection. have been researched under difierent initial conditions Firstlv several factors e.g. orifice on steam lines and the volume ratio of the gas steam spaces ofthe reactor and the boron tank, have effects on the pressure and water injection response time and other thermal hydraulic performance of the system Secondly the steam and fiquid comFllll. nication modes, namely the acting time and sequence ofthe action ofvalves connecting steam and liquid lines,have great influences oil the performance of the system Thirdly the limited pressure balance time(about 1.0s) can be achieved under the cold condition. This investiga-tion shows that GDBIS can be properly used in the 200 MW nuclear heating reactor.
-
56浏览
-
0点赞
-
0收藏
-
0分享
-
45下载
-
0评论
-
引用
【期刊论文】Experimental study of the transient characteristics of a natural circulation loop under SBLOCA
姜胜耀, J.H. Bo, s. Y. Jiang, Y.J. Zhang and C. w. Ma
,-0001,():
-1年11月30日
In order to understand the influences of various factors on the depressurization rate under small break LOCA occurring at the upper plenum in a natural circulation loop, a basic analysis has been carried out. It is shown that the depressurization rate is influenced by system pressure, back pressure, break area, water mass in the system, heating power, operational state of the second loop, and so on. Experimental results of flow and heat transfer are also presented in this paper. The experiment was carried out at the 5MW unclear heating reactor test loop HRTL-5. The transient processes are described and heat transfer coefficients are estimated. The results show that flashing improves the natural circulation and the heat transfer, so the wall temperature of the heated rod can be kept at a lower level and the reactor is safe. The flow oscillation, which leads to cyclical variations of important parameters, is described and its development mechanisms are studied. It is pointed out that the interaction of pressure decreasing and bubbles producing caused by flashing is the main reason of the flow oscillation.
-
64浏览
-
0点赞
-
0收藏
-
0分享
-
29下载
-
0评论
-
引用
【期刊论文】Experimental simulation study on start-up of the 5 MW nuclear heating reactor
姜胜耀, S.Y. Jiang. M.S. Yao, J.H. Bo, S.R. Wu
Nuclear Engiaeering and Design 158 (1995) 11-123,-0001,():
-1年11月30日
An experimental simulation study on the start-uD of a low temperature natural circulation nuclear heating reactor (5 MW developed by the Institute ol Nuclear Energy of Tsingbua University, Beijing) is presented The experiment was performed on the test loop (HRTL-5) which simulates the geometry and system design ol the 5 MW reactor The manifestation of difierenl kinds ot two-phase flow instability namely geysering flashing instability and low steam quality density wave instability on the start-uD are described The mechanism of flashing instabiIit)which has never been well studied In this field 1s especially interpreted Based Oll the study of these lnstabilitieg lt Is suggested that the start-uD process from Initial condition to boiling operation condition. should consist of three steps: increasing of Initial pressure by means of a noncondensabk gas (N,) start-up of the reactor at this pressurized condition (single-phase regime operation), and transition to a lower pressure boiling operation Three transition methods are +N34 discussed As a result of these studies the method of transition with low heat flux and low lnlet subcooling is proposed A stable start-up process of the 5 MW reactor is achieved by carefuI selection of the thermoh~draulic parameters.
-
76浏览
-
0点赞
-
0收藏
-
0分享
-
46下载
-
0评论
-
引用
姜胜耀, S.Y. Jiang, X. Yang and Y Zhang
,-0001,():
-1年11月30日
Based on a physical model of the test loop HRTL-5 simulating the 5MW nuclear heating reactor, a drift-flux model of two-phase flow has been derived, in which the sub-cooled boiling and saturated boiling in the heated section, condensation and void flashing in the adiabatic riser etc, are taken into account. In is suitable to ivestigate the natural circulation two-phase flow, expecially at heating reactor conditions, By introducing the concept of condensation boundary layer, a condensation formula has been derived and complemented into the drift-flux model, which was used to investigate the beharior of the HRTL-5 in our previous research works. Based on the mathematical model, a computer program has been developed. At first, through comparing the calculations with the experimental results, the parameters in the two-phase drift-flux model have been determined. Then calculations on the flow characteristics of HRTL-5 have been performed, including the simulating of the mass flow rate and the distribution of various physical variables. At last, the characteristic curves of natural circulation have been simulated; thereby, also usful experiences have been acquired.
-
53浏览
-
0点赞
-
0收藏
-
0分享
-
73下载
-
0评论
-
引用