Fire Science and Technology
Online ISSN : 1882-0492
Print ISSN : 0285-9521
ISSN-L : 0285-9521
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Volume 13, Issue Suppl
Displaying 1-15 of 15 articles from this issue
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Special Issue for SMiRT 11 Seminar #6 Fire Safety for Nuclear Power Plants
  • Introduction
    Kunio Kawagoe
    1993 Volume 13 Issue Suppl Pages S_i
    Published: 1993
    Released on J-STAGE: February 05, 2008
    DOIhttps://doi.org/10.3210/fst.13.S_i
    JOURNAL FREE ACCESS
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  • Conclusions from the Seminar
    Ulrich Schneider
    1993 Volume 13 Issue Suppl Pages S_ii-S_iii
    Published: 1993
    Released on J-STAGE: February 05, 2008
    DOIhttps://doi.org/10.3210/fst.13.S_ii
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  • Introduction of Nuclear Power Plants in Japan
    Kunio Kawagoe
    1993 Volume 13 Issue Suppl Pages S_1-S_4
    Published: 1993
    Released on J-STAGE: February 05, 2008
    DOIhttps://doi.org/10.3210/fst.13.S_1
    JOURNAL FREE ACCESS
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    This introductive paper shows Japanese NPP operating and planning. Safety organizations for NPP are described briefly.
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  • Fire Hazards Assessment for Pickering Nuclear Generation Station
    Steven P. Lee, Malcolm Rawlingson
    1993 Volume 13 Issue Suppl Pages S_5-S_11
    Published: 1993
    Released on J-STAGE: February 05, 2008
    DOIhttps://doi.org/10.3210/fst.13.S_5
    JOURNAL FREE ACCESS
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    This paper describes the approach used and the major finding of a recent fire hazards assessment of the Pickering Nuclear Generation Station.
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  • Fire Risk Assessment and Management in Nuclear Power Plants
    G. E. Apostolakis
    1993 Volume 13 Issue Suppl Pages S_12-S_39
    Published: 1993
    Released on J-STAGE: February 05, 2008
    DOIhttps://doi.org/10.3210/fst.13.S_12
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    A methodology for the assessment of risk due to fires in nuclear power plants is presented. This methodology integrates the important elements of a comprehensive approach, namely: 1. engineering knowledge of the response of the plant when a specified set of components is damaged; 2. statistical analysis of the available data regarding the occurrence of fires and their detection and suppression; 3. physical modeling of the thermal hazards (temperatures and heat fluxes) in a compartment fire; and 4. probabilistic modeling of the competition between fire growth time and detection and suppression time, as well as the propagation of uncertainties through the COMPBRN code, which calculates the thermal hazards. The use of the methodology in risk management is also discussed through an example.
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  • Fire Safety Problems with Older Nuclear Power Plants
    Ulrich Schneider, Ulrich Max
    1993 Volume 13 Issue Suppl Pages S_40-S_53
    Published: 1993
    Released on J-STAGE: February 05, 2008
    DOIhttps://doi.org/10.3210/fst.13.S_40
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    The fire risk of older nuclear power plants i.e. plants being more than 15 or 20 years under operation is a concern since in several plants serious fires occurred. Due to the rapid increase of knowledge in the field of fire science during the last three decade on the hand and with respect to public discussion about nuclear safety on the other, the responsible authorities permanently exert for the safety of older plants whereby the fire safety plays an increasing role. The report discusses experiences and method which were gathered and developed during the investigation of several older plants in Germany and the CSFR in the last decade. It related especially to the results of a survey in two German boiling water reactors (BWR 640 and BWR 670) which operate since 1969 and 1972 and a Russian pressure water reactor (WWER 440-V230) in the CSFR which came under operation in 1979. Conclusion of the report are that the fire safety of the Russian WWER 440-V230 is comparatively low. The proposed basic objectives of fire safety can not be fulfilled by this reactor type. It is mentioned that a Russian reactor of the same type in East-Germany was shut-down because of safety considerations immediately after German reunification. Inadequacy of fire safety was one of the main reasons which led to this decision.
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  • A Review of Experimental and Nuclear Studies Performed at CADARACHE on Hydrocarbon Fires
    R. Rzekiecki, J.C. Malet, C. Casselman, J.M. Such
    1993 Volume 13 Issue Suppl Pages S_54-S_62
    Published: 1993
    Released on J-STAGE: February 05, 2008
    DOIhttps://doi.org/10.3210/fst.13.S_54
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    The primary thermodynamic consequences of a fire in a room are evaluated through a zone model. In order to place a qualified numerical tool at the disposal of designers, project managers and safety analysts, an experimental programme started on large hydrocarbon pool fires in the "fire laboratories" at CADARACHE. Some outstanding results on single fire taking place in a single room are presented in this paper. Large scaled tests were performed on TBP/dodecane mixture involving up to 1000 l of mixture in a 3600 m3 concrete caisson and smaller ones on heavy oil and plastics. All the fires were controlled by ventilation management. Usually, the fire stopped around a 15% oxygen gas concentration and the initial transient pressure rise was the most important parameter for the mechanical resistance of the room and its associated venting system. The fire duration was short and re-ignitions were observed. Concerning the main variables, i.e. : Mean gas temperature, gas pressure, fire duration, released energy, exhaust flow rate, the calculated values from FLAMME 1 software package were in a good agreement with the experimental results. Associating the combustion code, FLAMME, with an accurate description of the whole venting system by LIQUINET code, provided more fitted calculates results.
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  • Study of Force - Ventilated Fires in Closed Space
    K. Mizuno, S. Tanaka, Y. Hasemi
    1993 Volume 13 Issue Suppl Pages S_63-S_82
    Published: 1993
    Released on J-STAGE: February 05, 2008
    DOIhttps://doi.org/10.3210/fst.13.S_63
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    Gas analysis and measurements of heat flux and temperature were made using a 50cm cubic model box with methanol as the fuel for grasping a phenomena that occur during force-ventilated fires in closed spaces. The criticality for heavy CO production (1-5 vol. %) can be described as a function of stoichiometric fuel to air ratio, and the CO concentration changes dramatically when the stoichiometric fuel to air ratio is approximately equal to 1.0. The combustion characteristics within the force-ventilated fire enclosure change due to the inlet and outlet conditions even if the other ventilation conditions (air supply rate, tray size) are the same. Further, gas analysis and measurements of temperature were made using a large model box (L=3.6m, W=2.4m, H=2.4m) with methane and propane as heat sources with controllable heat release rate for grasping the characteristics of smoke layer formation within the forced-ventilated fire enclosure which is highly air tight. Smoke layer formation within the force-ventilated fire enclosure is influenced by the air flow within the enclosure and temperature difference between the supply air and exhaust gas.
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  • Fire Experiments in a Closed Subcompartment of a Nuclear Power Plant
    K. Müller, R. Dobbernack
    1993 Volume 13 Issue Suppl Pages S_83-S_91
    Published: 1993
    Released on J-STAGE: February 05, 2008
    DOIhttps://doi.org/10.3210/fst.13.S_83
    JOURNAL FREE ACCESS
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    In Phase III of the HDR Safety Program, fires in the lower region of the HDR containment were investigated to solve open questions with respect to the protection of persons and the environment, and investigations of active fire protection components and protection concepts in full scale fires and their calculability.
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  • Fire Code Assessment During HDR Experiments
    M. Röwekamp, R. Dobbernack, K. Müller
    1993 Volume 13 Issue Suppl Pages S_92-S_101
    Published: 1993
    Released on J-STAGE: February 05, 2008
    DOIhttps://doi.org/10.3210/fst.13.S_92
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    Fire is one of the last problems in nuclear safety seen from the code side. Codes for fire prediction are normally involved in post calculations of convectional fires, with the smoke escaping through doors, windows, celling hatches. The fire situation inside nuclear power plants is very different to this conventional scenario.
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  • Fire Simulation in Nuclear Power Plants with the Code MRFC
    Ulrich Schneider, Ulrich Max
    1993 Volume 13 Issue Suppl Pages S_102-S_115
    Published: 1993
    Released on J-STAGE: February 05, 2008
    DOIhttps://doi.org/10.3210/fst.13.S_102
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    The code MRFC(Multi Room Fire Code) has been developed since 1984. Its applicability has been proved by comparison with a number of full scale tests performed in a nuclear research reactor with the HDR Safety Program. During the whole test program calculations were made with different fire codes as to check their applicability. Four of those codes use zone modeling as a physical basis (MRFC, DOB, CCFM, FAST). The other codes used field models and system models. The system code were especially developed in reactor industry as to simulate thermodynamically processes in containment e.g. hydrogen distributions. At the beginning of the research program a wide range of computer results was obtained with partly large differences compared to the experimental data. After specific improvements in the codes the spectrum of calculation results became much smaller and reflected the experimental data at least at several points. The results obtained with zone models were comparable to those of the much more complicated field models and system codes, i.e. the last were not superior as to be expected. It has been learned from the tests, that the temperatures of the fire gases reduce rapidly after fire compartment due to very high entrainments of cold gases into the hot gas layers and by a significant heat transfer to the concrete structure.
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  • HDR Reactor Containment Fire Simulation
    John A. Rockett, Esko Eloranta, Olavi Keski-Rahkonen
    1993 Volume 13 Issue Suppl Pages S_116-S_134
    Published: 1993
    Released on J-STAGE: February 05, 2008
    DOIhttps://doi.org/10.3210/fst.13.S_116
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    Fire tests at the German test reactor HDR were simulated using a Japanese zone model, BRI2. Eight and ten room models of the containment building were developed. Critical phenomena occurring during simulation were explored. BRI2 can be used for this type of work but care must be exercised where a side wind increases entrainment by the fire plume. Horizontal vents were described by effective vertical vents. Effect of location of the vent to ambient was found critical for cases where severely oxygen limited burning occurred.
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  • An HMS/RRAC Analysis of A High-Level Radioactive Waste Tank Farm
    J. R. Travis, B. D. Nichols, J. W. Spore, T. L. Win
    1993 Volume 13 Issue Suppl Pages S_135-S_167
    Published: 1993
    Released on J-STAGE: February 05, 2008
    DOIhttps://doi.org/10.3210/fst.13.S_135
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    It has been observed that a high-level radioactive waste tank generated quantities of hydrogen and nitrous oxide mixture that are potentially well within flammability limits. These gases are produced from chemical and nuclear decay reaction in a slurry of radioactive waste materials. The slurry is covered by a thick crust and containing sodium nitrate and nitrite salts. Significant amounts of combustible and reactant gases accumulate under the crust over a 110- to 120-day period. These gases cause the crust to rupture, allowing the gases to vent into the air cover-gas space above the crust. We postulated an ignition source for the hydrogen/nitrousoxide/air mixture after it has vented into the cover gas, and we calculated the resulting pressure and temperature loading on the double-walled waste tank using the three-dimensional, time-dependent fluid dynamics coupled with the chemical kinetic computer code HMS (Hydrogen Mixing Studies).
    The waste tank farm has a ventilation system designed to maintain a slight negative gage pressure during normal operation. We modeled the ventilation system with TRAC (Transient Reactor Analysis Code), and we coupled these two best-estimate accident analysis tools to model the ventilation system response to pressures and temperatures generated by the hydrogen combustion. Significant pressure are produced by this event, which could possibly threaten the tank's integrity.
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  • Fire Risk from Electric Parts
    - Fire Cases initiated from Non - fused Breaker -
    Osami Sugawa, Kunio Kawagoe
    1993 Volume 13 Issue Suppl Pages S_168-S_175
    Published: 1993
    Released on J-STAGE: February 05, 2008
    DOIhttps://doi.org/10.3210/fst.13.S_168
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    This paper describes two fire cases occurred in electric machine rooms which have supported information processors of water level observatories and control systems. Both fires might be initiated by failure of non-fused breaker(s). This type of fire occurred twice for 4 years in about 700 of the similar systems. If no attention paid to fire risk on non-fuse breakers, we may have the same kind of fire in the control system of nuclear power plants and related process facilities because non-fuse breaker is quite common parts and is used every systems. This paper describes also the concentrations of halogens adhered on the surface of the electrical system before and after a cleaning. The concentration of halogens including products from Halon 1301 and burnt PVC cables may help the corrosion risk assessment of the system.
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  • Standards for Fire Safety of Indian
    Pressurized Heavy Water Reactors (PHWRS)
    N. K. Agarwal
    1993 Volume 13 Issue Suppl Pages S_176-S_180
    Published: 1993
    Released on J-STAGE: February 05, 2008
    DOIhttps://doi.org/10.3210/fst.13.S_176
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    This paper introduces briefly the standards of fire safety for Indian nuclear power plants of pressurized heavy water reactors.
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