FDS simulation of the fuel fireball from a hypothetical commercial airliner crash on a generic nuclear power plant (Englisch)

in Nuclear Engineering and Design ; 239 , 10 ; 2056-2069
Nuclear Engineering and Design
Elsevier B.V. ; 2009

AbstractIn the aftermath of 9/11 events it became clear that the impact of a fast flying commercial airliner hitting the NPP could no longer be excluded as a potential external hazard threatening the nuclear power plant (NPP) safety. One of the potential consequences of the impact is the occurrence of a fireball, large enough to engulf the entire NPP. The knowledge about fireballs from air crashes is rather poor since it is only based on footage shot by chance. From careful physical and chemical examinations using first principles, it can be concluded that the physics and chemistry of the kerosene fireball are similar to BLEVE fireballs in gas tank accidents which have been studied during the last decades. The knowledge from these analyses can be applied to air crash fireball analysis.In order to obtain an adequate understanding of the potential hazards to a NPP engulfed by a fireball a detailed analysis of the fireball is necessary. It is only by a detailed analysis that the effect of the NPP structures on the evolution of the fireball can be derived. Though the safety-relevant parts of the NPP are strong concrete structures, according to IAEA regulations the hypothesized entry of combustion products into ventilation or air supply systems and the entry of fuel into buildings through normal openings have to be analyzed in detail. This requires local transient values of the safety-relevant fireball parameters. With the NPP being a very large structure an adequately detailed simulation requires large computing grids and substantial computing power.With the release of Version 5 of the Fire Dynamic Simulator (FDS) from NIST in 2007 a simulation tool is now available which is capable to perform simulations of large fireballs on sufficiently large computing grids. These fireball simulations can be performed also by any other CFD code in which the relevant models have been implemented.The FDS fireball simulation capabilities were validated with the help of a well-documented fireball event, in which 5.9 to of propane were burnt during a BLEVE impact experiment conducted by the German BAM in 1999.To demonstrate the applicability of FDS to nuclear safety analysis a simulation of the impact of a 90 to fireball on a generic NPP was performed. The results are presented in this paper and show that FDS release Version 5 is an adequate tool to analysis the effect of a fireball on a NPP, even if the largest possible amount of kerosene involved in the crash is assumed.The work presented in this paper is based on codes, papers, footage and material that are freely available on the Internet. The paper does not use any information that is not freely available on the Internet.

Wie erhalte ich diesen Titel?

Download ist DRM geschützt.

Kommerziell Vergütung an den Verlag: 36,00 € Grundgebühr: 4,00 € Gesamtpreis: 40,00 €
Akademisch Vergütung an den Verlag: 36,00 € Grundgebühr: 2,00 € Gesamtpreis: 38,00 €


Inhaltsverzeichnis – Band 239, Ausgabe 10

Zeige alle Jahrgänge und Ausgaben

Die Inhaltsverzeichnisse werden automatisch erzeugt und basieren auf den im Index des TIB-Portals verfügbaren Nachweisen der enthaltenen Aufsätze. Die Anzeige der Jahrgänge kann aufgrund fehlender Aufsatznachweise unvollständig oder lückenhaft sein, obwohl die Zeitschrift komplett in der TIB verfügbar ist.

Simplified theory for flow pattern prediction in perforated tubes
Singh, Raj Kumar / Rama Rao, A. | 2009
Modeling of low-pressure subcooled boiling flow of water via the homogeneous MUSIG approach
Chen, Erfeng / Li, Yanzhong / Cheng, Xianghua / Wang, Lei | 2009
A study on a characteristic of stem friction coefficient for motor operated flexible wedge gate valve
Kim, Dae-Woong / Park, Sung-Geun / Lee, Sang-Guk / Kang, Shin-Cheul | 2009
Creep-fatigue design evaluations including daily load following operations for the advanced burner test reactor
Koo, Gyeong-Hoi / Sienicki, James J. / Tzanos, Constantine P. / Moisseytsev, Anton | 2009
Phenomena of reverse momentum pulse and fluid leak after poison injection in the shut down system of PHWR
Singh, Raj Kumar / Sinha, Sunil Kumar / Rao, A. Rama | 2009
MOOSE: A parallel computational framework for coupled systems of nonlinear equations
Gaston, Derek / Newman, Chris / Hansen, Glen / Lebrun-Grandié, Damien | 2009
Mixture loss coefficient of safety valves used in nuclear plants
Benbella, Shannak | 2009
Ballistic properties of multilayered concrete shields
Ben-Dor, G. / Dubinsky, A. / Elperin, T. | 2009
Modeling the effects of nuclear environments on crevice corrosion of pure nickel by coupling of phase and polarization behavior
Hoffmeister, Hans | 2009
Wavelet-based angular dependence analysis of the heterogeneous calculation on MOX fuel lattice
Zheng, Youqi / Wu, Hongchun / Cao, Liangzhi | 2009
Effects of working fluid and shaft rotation speed on the performance of HTR plants and the size of CBC turbo-machine
El-Genk, Mohamed S. / Tournier, Jean-Michel | 2009
Validation of a new continuous Monte Carlo burnup code using a Mox fuel assembly
El bakkari, B. / El Bardouni, T. / Merroun, O. / El Younoussi, C. / Boulaich, Y. / Boukhal, H. / Chakir, E. | 2009
A CFD model of two-phase flow in BWRs with results of sensitivity and uncertainty analysis
Kocar, Cemil / Sökmen, Cemal Niyazi | 2009
Development and application of a dual RELAP5-3D-based engineering simulator for ABWR
Yang, Chung-Yu / Liang, Thomas K.S. / Pei, B.S. / Shih, C.K. / Chiang, S.C. / Wang, L.C. | 2009
Control rod drop analysis by finite element method using fluid–structure interaction for a pressurized water reactor power plant
Yoon, K.H. / Kim, J.Y. / Lee, K.H. / Lee, Y.H. / Kim, H.K. | 2009
The estimation of lifetime distribution of Alloy 800 steam generator tubing
Pandey, M.D. / Datla, S. / Tapping, R.L. / Lu, Y.C. | 2009
Scaling of passive condenser system for separate effect testing
Revankar, Shripad T. / Oh, Seungmin / Zhou, Wenzhong / Henderson, Gavin | 2009
A new method for estimating heat flux in superheater and reheater tubes
Purbolaksono, J. / Khinani, A. / Rashid, A.Z. / Ali, A.A. / Ahmad, J. / Nordin, N.F. | 2009
Film boiling heat transfer and vapour film collapse on spheres, cylinders and plane surfaces
Jouhara, Hussam / Axcell, Brian P. | 2009
Performance improvement of artificial neural networks designed for safety key parameters prediction in nuclear research reactors
Mazrou, Hakim | 2009
Study of the radiotoxicity of actinides recycling in boiling water reactors fuel
François, J.L. / Guzmán, J.R. / Martín-del-Campo, C. | 2009
Neutronic and nonproliferation characteristics of (PuO2–UO2) and (PuO2–ThO2) as fast reactor fuels
Chirayath, Sunil Sunny / Hollenbeck, Gordon / Ragusa, Jean / Nelson, Paul | 2009
RELAP5-3D modeling of PWR steam generator condensation experiments at the Oregon State University APEX facility
Woods, Brian G. / Collins, Brian | 2009
Two phase flow 1D turbulence model for poly-disperse upward flow in a vertical pipe
Al Issa, S. / Lucas, D. | 2009
Local thermal–hydraulic behaviour in tight 7-rod bundles
Cheng, X. / Yu, Y.Q. | 2009
Investigation of forced convection heat transfer of supercritical pressure water in a vertically upward internally ribbed tube
Wang, Jianguo / Li, Huixiong / Guo, Bin / Yu, Shuiqing / Zhang, Yuqian / Chen, Tingkuan | 2009
Experimental and analytical investigation of intermittent flame effect on radiant emission for pool fires
Ferng, Y.M. / Lin, C.H. | 2009
Foam formation in oxidic pool with application to MCCI real material experiments
Tourniaire, B. / Dufour, E. / Spindler, B. | 2009
SCWR subchannel code ATHAS development and CANDU-SCWR analysis
Shan, Jianqiang / Zhang, Bo / Li, Changying / Leung, Laurence K.H. | 2009
A stepwise development and validation of a RANS based CFD modelling approach for the hydraulic and thermal-hydraulic analyses of liquid metal flow in a fuel assembly
Chandra, Laltu / Roelofs, Ferry / Houkema, Michiel / Jonker, Bouke | 2009
Experimental investigation on heat transfer from a heated rod with a helically wrapped wire inside a square vertical channel to water at supercritical pressures
Li, Hongzhi / Wang, Haijun / Luo, Yushan / Gu, Hongfang / Shi, Xiaobao / Chen, Tingkuan / Laurien, Eckart / Zhu, Yu | 2009
Experimental investigation of turbulent flow through spacer grids in fuel rod bundles
Caraghiaur, Diana / Anglart, Henryk / Frid, Wiktor | 2009
Experimental study of the characteristics of the flow in the first rows of tube banks
Olinto, Cláudio R. / Indrusiak, Maria Luiza S. / Endres, Luiz Augusto M. / Möller, Sergio V. | 2009
Investigation of surface microgeometry and the active nucleation cavities using AFM
Chen, Peipei / Wu, Wen / Jones, Barclay G. | 2009
Analysis of the suction effect on the mass transfer when using the heat and mass transfer analogy
de la Rosa, J.C. / Herranz, L.E. / Muñoz-Cobo, J.L. | 2009
FDS simulation of the fuel fireball from a hypothetical commercial airliner crash on a generic nuclear power plant
Luther, Wolfgang / Müller, W. Christoph | 2009
Direct containment heating integral effects tests in geometries of European nuclear power plants
Meyer, Leonhard / Albrecht, Giancarlo / Caroli, Cataldo / Ivanov, Ivan | 2009
ZBDD algorithm features for an efficient Probabilistic Safety Assessment
Jung, Woo Sik | 2009
Generic CANDU 6 plant severe accident analysis employing SCAPSIM/RELAP5 code
Dupleac, Daniel / Mladin, Mirea / Prisecaru, Ilie | 2009
Application of coupled code technique to a safety analysis of a standard MTR research reactor
Hamidouche, Tewfik / Bousbia-Salah, Anis / Si-Ahmed, El Khider / Mokeddem, Mohamed Yazid / D’Auria, Franscesco | 2009
Development of a risk-informed accident diagnosis and prognosis system to support severe accident management
Ahn, Kwang-Il / Park, Soo-Yong | 2009
Estimation of precursor concentration in a research reactor by using second order sliding mode observer
Qaiser, S. Hameed / Bhatti, Aamer Iqbal / Iqbal, Masood / Samar, Raza / Qadir, Javed | 2009
Dynamic model for control system design and simulation of a low temperature nuclear reactor
Dong, Zhe / Huang, Xiaojin / Feng, Junting / Zhang, Liangju | 2009
Tension metastable fluid nuclear particle Detector—Qualification and comparisons
Lapinskas, J. / Smagacz, P. / Xu, Y. / Taleyarkhan, R.P. | 2009
Fuel cycle analysis of TRU or MA burner fast reactors with variable conversion ratio using a new algorithm at equilibrium
Salvatores, Massimo / Chabert, Christine / Fazio, Concetta / Hill, Robert / Peneliau, Yannick / Slessarev, Igor / Yang, Won Sik | 2009
A new method for rapid computation of transient fuel cycle material balances
Scopatz, Anthony M. / Schneider, Erich A. | 2009
A thermal model of the immobilization of low-level radioactive waste as grout in concrete vaults
Shadday, Martin A. Jr. | 2009
Radioactive waste management plan for the PBMR (Pty) Ltd fuel plant
Makgae, Mosidi E. | 2009
Improvement in accuracy of the measurements of residual stresses due to circumferential welds in thin-walled pipe using Rayleigh wave method
Akhshik, Siamak / Moharrami, Rasool | 2009
Interim storage of power reactor spent nuclear fuel (SNF) and its potential application to SNF separations and closed fuel cycle
Levy, Salomon | 2009
Heat transfer model of single-phase natural circulation flow under a rolling motion condition
Si-chao, Tan / Su, G.H. / Pu-zhen, Gao | 2009

Ähnliche Titel