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[en] The instantaneous jamming of one RCP shaft accident of Tianwan NPS was analyzed by using the thermal-hydraulic code DINAMIKA-97. This paper presents the main calculation and analysis results, which show that the acceptance criteria are met in the accident. (authors)
Journal
China Nuclear Power; ISSN 1674-1617; 
; v. 4(2); p. 174-179
; v. 4(2); p. 174-179
[en] The long fuel cycle will be implemented in Tianwan Nuclear Power Station, and the design basis accident needs to be re-analyzed since the change of core design. The large break LOCA was analyzed in the paper. Based on the input data and calculation assumption, the most conservative calculated case was obtained through the conservative analysis of the axial power distribution and the ECCS. It is shown that the accept criteria are satisfied in the large break LOCA on long fuel cycle, and the safety margin of the core design is large enough. (authors)
Journal
Atomic Energy Science and Technology; ISSN 1000-6931; ; v. 48(11); p. 1998-2003
; v. 48(11); p. 1998-2003
[en] Tianwan Nuclear Power Station owns two WWER-1000 reactors imported from Russia at present. The two reactors are put into commercial operation in 2007 and operating in the fourth fuel cycle in 2010. This report briefly describes the characteristics of fuel assemblies and in-core loadings for Tianwan Nuclear Power Station WWER-1000 reactors under annual refueling scheme. As well as the plan of 18-month fuel cycle, which will be introduced to Tianwan Nuclear Power Station WWER-1000 reactors in the future, is presented in the report. (Authors)
Source
Vidovszky, I. (Kiadja az MTA KFKI Atomenergia Kutatointezet, Budapest (Hungary)); Fortum Nuclear and Thermal (Finland); VTT Technical Research Centre of Finland (Finland); Lappeenranta University of Technology (Finland); The Aalto University School of Science and Technology (Finland); Paks NPP Ltd., Paks (Hungary); KFKI Atomic Energy Research Institute, Budapest (Hungary); Budapest University of Technology and Economics, Institute of Nuclear Techniques, Budapest (Hungary); Hungarian Atomic Energy Authority (Hungary); VUJE, Inc., Trnava (Slovakia); Slovak University of Technology, Faculty of Electrical Engineering and Information Technology, Department of Nuclear Physics and Technology, Bratislava (Slovakia); Nuclear Regulatory Authority of the Slovak Republic (Slovakia); Nuclear Research Institute Rez plc, Husinec-Rez (Czech Republic); Skoda JS a.s., Plzen (Czech Republic); CEZ , Inc. (Czech Republic); University of Defence in Brno (Czech Republic); The University of West Bohemia Faculty of Applied Sciences (Czech Republic); Russian Research Center 'Kurchatov Institute', Moscow (Russian Federation); JSC OKB 'GIDROPRESS' (Russian Federation); JSC 'TVEL' (Russian Federation); Forschungszentrum Dresden- Rossendorf, Institute of Safety Research, Dresden (Germany); GRS mbH (Germany); Studsvik Scandpower GmbH (Germany); TUEV SUED Industrie Service, Energy and Technology (Germany); Gesellschaft fuer Anlagen - und Reaktorsicherheit (Germany); Studsvik Scandpower (Sweden); State Scientific and Technical Centre on Nuclear and Radiation Safety of Ukraine, Kyiv (Ukraine); Nuclear and Radiation Safety Centre (Armenia); Jiangsu Nuclear Power Corporation, Tianwan Nuclear Power Station (China); Jiangsu Nuclear Power Corporation (China); 790 p; ISBN 978-963-372-643-3 (OE); ; Oct 2010; p. 1-10; 20. Atomic Energy Research Symposium on WWER Physics and Reactor Safety; Hanasaari, Espoo (Finland); 20-24 Sep 2010; 7 figs.; 2 tabs.
; Oct 2010; p. 1-10; 20. Atomic Energy Research Symposium on WWER Physics and Reactor Safety; Hanasaari, Espoo (Finland); 20-24 Sep 2010; 7 figs.; 2 tabs.
[en] This paper briefly describes the test purposes, test items, test schedules and test equipment's for reload startup physics test's on Unit 1 and 2 of Tianwan Nuclear Power station. Then, an overview of the previous thrice tests and evaluations on the tests results are presented. In the end, the paper shows the development and work direction of optimization project for reload startup physics tests on Unit 1 and 2 of Tianwan Nuclear Power station. (Authors)
Source
Vidovszky, I. (Kiadja az MTA KFKI Atomenergia Kutatointezet, Budapest (Hungary)); Fortum Nuclear and Thermal (Finland); VTT Technical Research Centre of Finland (Finland); Lappeenranta University of Technology (Finland); The Aalto University School of Science and Technology (Finland); Paks NPP Ltd., Paks (Hungary); KFKI Atomic Energy Research Institute, Budapest (Hungary); Budapest University of Technology and Economics, Institute of Nuclear Techniques, Budapest (Hungary); Hungarian Atomic Energy Authority (Hungary); VUJE, Inc., Trnava (Slovakia); Slovak University of Technology, Faculty of Electrical Engineering and Information Technology, Department of Nuclear Physics and Technology, Bratislava (Slovakia); Nuclear Regulatory Authority of the Slovak Republic (Slovakia); Nuclear Research Institute Rez plc, Husinec-Rez (Czech Republic); Skoda JS a.s., Plzen (Czech Republic); CEZ , Inc. (Czech Republic); University of Defence in Brno (Czech Republic); The University of West Bohemia Faculty of Applied Sciences (Czech Republic); Russian Research Center 'Kurchatov Institute', Moscow (Russian Federation); JSC OKB 'GIDROPRESS' (Russian Federation); JSC 'TVEL' (Russian Federation); Forschungszentrum Dresden- Rossendorf, Institute of Safety Research, Dresden (Germany); GRS mbH (Germany); Studsvik Scandpower GmbH (Germany); TUEV SUED Industrie Service, Energy and Technology (Germany); Gesellschaft fuer Anlagen - und Reaktorsicherheit (Germany); Studsvik Scandpower (Sweden); State Scientific and Technical Centre on Nuclear and Radiation Safety of Ukraine, Kyiv (Ukraine); Nuclear and Radiation Safety Centre (Armenia); Jiangsu Nuclear Power Corporation, Tianwan Nuclear Power Station (China); Jiangsu Nuclear Power Corporation (China); 790 p; ISBN 978-963-372-643-3 (OE); ; Oct 2010; p. 1-7; 20. Atomic Energy Research Symposium on WWER Physics and Reactor Safety; Hanasaari, Espoo (Finland); 20-24 Sep 2010; 3 figs.
; Oct 2010; p. 1-7; 20. Atomic Energy Research Symposium on WWER Physics and Reactor Safety; Hanasaari, Espoo (Finland); 20-24 Sep 2010; 3 figs.
[en] Six TVS-2M type pilot fuel assemblies were loaded starting from the 5th fuel cycle at Tianwan NPS Unit 1, and would be under 4-year in-core fuel operation lifetime test from the 5th cycle to the 8th fuel cycle. Based on in-core thermal-hydraulic analysis, as well as the thermal-hydraulic test measurement and fuel assembly deformation inspection for the TVS-2M type pilot fuel assemblies, it is verified that the calculation mode of the thermal-hydraulic design code is reasonable and the calculation results are in good agreement with test results. The results show that the TVS-2M type fuel assembly and the AFA fuel assembly have a good compatibility during reactor operation, and the core operation reliability and safety can also be ensured during the transition fuel cycles. (authors)
Journal
Atomic Energy Science and Technology; ISSN 1000-6931; ; v. 48(9); p. 1605-1608
; v. 48(9); p. 1605-1608
[en] During the 5th refueling outage of Tianwan Nuclear Power Station Unit l, according to the fuel assembly inspection results, emergency refueling design has been carried out. The in-core loading scheme of Unit l Cycle 6 has special characteristics from normal refueling. For example, fuel loading is asymmetry, some burned fuel assemblies are moved to symmetrical sectors, and in-core power distribution is asymmetry etc. In addition, in-core loading scheme has been considered the requirement on positions of TVS-2M pilot fuel assemblies. Verified by physics tests and in-core measurement system at beginning of cycle 6, design results of in-core loading pattern meet all measurement criteria and requirements, and in-core operation conditions conform to design anticipate. (authors)
Journal
Atomic Energy Science and Technology; ISSN 1000-6931; ; v. 47(suppl.); p. 160-163
; v. 47(suppl.); p. 160-163
[en] At year of 2017, Tianwan Nuclear Power Station (TNPS) Unit 3 has finished first physical start-up without neutron sources. Relevant regulations and standards in China did not impose requirement on the physical start-up of Pressurized Water Reactors (PWR) for use of external neutron sources, but neutron flux monitoring and critical safety should be emphasized during start-up. Some strict technical measures and management measures were adopted during physical start-up of VVER reactors. These measures ensured that the sub-criticality of the reactor core is reliably monitored within the 'start-up interval', and further that the entire physical start-up process is safe and controllable. Based on the analysis of first physical starting process and safety measures for TNPS Unit 3, the theory and experimental data shown that the physical start-up of VVER reactor without external neutron sources was a mature and safe technology. (authors)
Journal
Nuclear Safety (Beijing); ISSN 1672-5360; ; v. 17(5); p. 7-13
; v. 17(5); p. 7-13
[en] The core continued to heat up due to the loss of cooling under accident conditions. The core would damage as it is uncovered for a long time. The reactor core exit temperature (CET) and the reactor vessel level (RVL) can provide an indirect indication of inadequate core cooling. CET and the containment dose rate are the master criteria in the method of core damage assessment, which is based on Westinghouse Owners Group Core Damage Assessment Guidance (CDAG). RVL, as one of the assistant parameters, can be used to validate the assessment result. In some nuclear power plant, CET, which is unused under sever accident condition, must be replaced by some other parameters. Based on the analysis of sever accident sequence, RVL would be discussed to be used in the current method of core damage assessment as a master criterion. (authors)
Journal
Atomic Energy Science and Technology; ISSN 1000-6931; ; v. 48(suppl.); p. 385-388
; v. 48(suppl.); p. 385-388
[en] Tianwan NPP Units l and 2 plans to transit to long fuel cycle from the year of 2014. The new type fuel assembly 'TVS-2M' will be introduced into the reactor core composed by AFA assemblies. After three fuel cycles, the reactor core will be loaded by all TVS-2M fuel assemblies and realize long fuel cycle. The thermal-hydraulic analysis should be performed again due to the change of fuel assembly structure. This paper presents the thermal-hydraulic analysis procedure and method for the steady-state of VVER reactors, and re-analyzes the thermal-hydraulic characteristic of the mixed core, which include five types of core loading during transition. It turned out that the mixed core steady-state design is still fitted to the requirements for thermal-hydraulic design. (authors)
Journal
Nuclear Safety (Beijing); ISSN 1672-5360; ; v. 12(4); p. 64-68
; v. 12(4); p. 64-68
[en] Highlights: • DRWM, for dynamic rod worth measurement, is an advanced method to measure the control rods worth in nuclear plants. • It can shorten more than ten hours compared with traditional method. • In this paper, correction factors calculation, experiment design, and final results are offered. • It shows that the advanced way is applied on nuclear plants successfully. • Also, the influencing factors are given, which can help to improve this method. - Abstract: Control rod worth measurement is very important in physical experiments before every cycle of nuclear plants. The traditional method is boron dilution method. DRWM (for Dynamic Rod Worth Measurement) (Chao et al., 2000) is an advanced method developed by Westinghouse and Electric Power Research Center. The main idea is to record the current signals from reactors, which is converted as reactivity by using inverse dynamic method. Besides, corrections are needed to get a good result. In China, an advanced reactivity meter made by China Institute of Atomic Energy is applied in a VVER. VVER is the abbreviation of Vodo-Vodyanoi Energetichesky Reactor in Russian. It is one kind of PWR using hexagonal fuel assembly developed by Russia. This paper gives the application of dynamic rod worth measurement in a VVER in Jiangsu Nuclear Plants. The correction coefficient calculations, experimental details and results would be introduced.
Journal