• Title/Summary/Keyword: Detonation Transition

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INVESTIGATIONS ON THE RESOLUTION OF SEVERE ACCIDENT ISSUES FOR KOREAN NUCLEAR POWER PLANTS

  • Kim, Hee-Dong;Kim, Dong-Ha;Kim, Jong-Tae;Kim, Sang-Baik;Song, Jin-Ho;Hong, Seong-Wan
    • Nuclear Engineering and Technology
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    • v.41 no.5
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    • pp.617-648
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    • 2009
  • Under the government supported long-term nuclear R&D program, the severe accident research program at KAERI is directed to investigate unresolved severe accident issues such as core debris coolability, steam explosions, and hydrogen combustion both experimentally and numerically. Extensive studies have been performed to evaluate the in-vessel retention of core debris through external reactor vessel cooling concept for APR1400 as a severe accident management strategy. Additionally, an improvement of the insulator design outside the vessel was investigated. To address steam explosions, a series of experiments using a prototypic material was performed in the TROI facility. Major parameters such as material composition and void fraction as well as the relevant physics affecting the energetics of steam explosions were investigated. For hydrogen control in Korean nuclear power plants, evaluation of the hydrogen concentration and the possibility of deflagration-to-detonation transition occurrence in the containment using three-dimensional analysis code, GASFLOW, were performed. Finally, the integrated severe accident analysis code, MIDAS, has been developed for domestication based on MELCOR. The data transfer scheme using pointers was restructured with the modules and the derived-type direct variables using FORTRAN90. New models were implemented to extend the capability of MIDAS.

A Study on the Characteristics of the interface in Tube / Tubesheet of the Nuclear Steam Generator by Explosive Bonding (폭발접합된 원자력 증기발생기 튜브/튜브시트 계면 특성에 관한 연구)

  • 이병일;공창식;심상한;강정윤;이상래
    • Explosives and Blasting
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    • v.17 no.4
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    • pp.32-50
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    • 1999
  • This study deals with interface charactristics of tube and tubesheet of the nuclear steam generator by the explosive expansion in order to take advantage of optimum expansion ratio, pull-out strength and leakage tightness and improvement of the resisitance on the stress corrosion cracking for low residual stress. The paper also show the relationship between roll, hydraulic and explosive expansion. The results obtain are as follows (1) Because of the explosive bonding is to use the high speed pressure and energy by the explosive, workability is good, bonding region is homogenous (2) Expansion ratio is 2.7%, Pull-out strength 850kg, Leakage strength $500kg/cm^2$. Clearance gap is 10~30mm in case of explosive expansion and interface structure of the tube and tubesheet is optimum condition. (3) As the transition region of the explosive expansion is inactive, the resistance of the stress corrosion cracking is increases 30~40% compare to the roll and hydraulic expansion.

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Numerical Simulation of Shock-Induced Combustion on Adaptive Mesh (적응격자를 이용한 충격파 유도 연소장 해석)

  • Kim, Sang-Hoon;Choi, Jeong-Yeol;Oh, Se-Jomg
    • Proceedings of the Korean Society of Propulsion Engineers Conference
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    • 2010.05a
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    • pp.397-400
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    • 2010
  • Unstructured adaptive grid flow simulation is applied to the calculation of high speed compressible flow of inert and reactive gas mixtures. Computational results are presented for the case of premixed hydrogen-air supersonic flow over a 2-D wedge. In such a configuration, combustion may be triggered behind the oblique shock wave and transition to an oblique detonation wave is eventually obtained. It is shown that the solution adaptive procedure implemented is able to correctly define the important wave front.

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NUMERICAL ANALYSIS OF THE HYDROGEN-STEAM BEHAVIOR IN THE APR1400 CONTAINMENT DURING A HYPOTHETICAL TOTAL LOSS OF FEED WATER ACCIDENT (APR1400의 급수완전상실사고 시 격납건물 내에서 수소와 수증기의 3차원 거동에 대한 수치해석)

  • Kim Jongtae;Hong Seong-Wan;Kim Sang-Baik;Kim Hee-Dong
    • Journal of computational fluids engineering
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    • v.10 no.3 s.30
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    • pp.9-18
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    • 2005
  • During a hypothetical severe accident in a nuclear power plant (NPP), hydrogen is generated by the active reaction of fuel-cladding and steam in the reactor pressure vessel and released with steam into the containment. In order to mitigate hydrogen hazards possibly occurred in the NPP containment, hydrogen mitigation system (HMS) is usually adopted. The design of the next generation NPP (APR1400) designed in Korea specifies 26 passive autocatalytic recombiners and 10 igniters installed in the containment for the hydrogen mitigation. in this study, the analysis of the hydrogen and steam behavior during a total lose of feed water (TLOFW) accident in the APR1400 containment has been conducted by using the CFD code GASFLOW. During the accident, a huge amount of hot water, steam, and hydrogen is released in the in-containment refueling water storage tank (IRWST). The current design of the APR1400 includes flap-type dampers at the IRWST vents which are operated depending on the pressure difference between inside and outside of the IRWST. it was found that the flaps strongly affects the flow structure of the steam and hydrogen in the containment. The possibilities of a flame acceleration and transition from deflagration to detonation (DDT) were evaluated by using Sigma-Lambda criteria. Numerical results indicate the DDT possibility could be heavily reduced in the IRWST compartment when the flaps are installed.

Synthesis and Characterization of Insensitive Energetic Plasticizer (둔감 에너지 가소제 합성 및 특성 분석)

  • Lee, Woonghee;Kim, Minjun;Park, Youngchul;Lee, Bumjae
    • Journal of the Korean Society of Propulsion Engineers
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    • v.20 no.6
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    • pp.11-17
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    • 2016
  • BTTN and TMETN are representative energetic plasticizers used for various propellants. However these compounds are sensitive relatively. So, in order to develop insensitive energetic plasticizer, this study attempted to synthesize derivative of triazole, 4,5-bis(azidomethyl)-(2-methoxyethyl)-1,2,3- triazole (DAMETR). Also, the prepared compound was characterized by NMR, IR spectroscopy, and physicochemical properties such as glass transition temperature, melting point, decomposition temperature, density, viscosity and impact sensitivity. In addition, the heats of formation (${\Delta}H_f$) and detonation properties (pressure and velocity) of DAMETR were calculated using Gaussian 09 and EXPLO5 programs. Especially, 1-DAMETR(>50 J) was more insensitive than BTTN(1 J) and TMETN(9.2 J).

The Study on the Synthesis of Triazole Derivatives as Energetic Plasticizer (트리아졸 계열의 에너지 가소제 합성 연구)

  • Lee, Woonghee;Kim, Minjun;Park, Youngchul
    • Journal of the Korean Society of Propulsion Engineers
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    • v.20 no.2
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    • pp.31-38
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    • 2016
  • Most of propellants that is used widely in the world release toxic gases such as methane gas and carbon dioxide during combustion which are noxious to the environment. This study established a synthetic process of a high nitrogen containing derivative of triazole, 4,5-bis(azidomethyl)-methyl-1,2,3-triazole (DAMTR), which can be applied as energetic plasticizer to environmental concerns. Also, the compound was characterized by NMR, IR spectroscopy, and physical properties such as glass transition temperature, melting point, decomposition temperature, density, impact sensitivity, viscosity and volatility were measured. In addition, the heats of formation (${\Delta}H_f$) and detonation properties (pressure and velocity) of DAMTR were calculated using Gaussian 09 and EXPLO5 programs.