A Study on the Technigues of Fire Hazard
Analysis for Nuclear Power Plants
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Abstract
Fire prevention codes for nuclear power plants in Taiwan comply with 10 CFR 50.48Appendix A General Design Criterion 3 (GDC 3) in 10 CFR 50, 10CFR50 Appendix R and local fire code etc. But local fire code is unsuitable for nuclear power plants in some places, such as turbine generation rooms, cable spreading rooms etc. Besides, with the renew of fire codes, existing nuclear power plants which run for decades are hard to answer the requirements due to spacing and structure. Furthermore, nuclear power plants in Taiwan adopt U.S. fire prevention codes, causing the difficulties in examination and requirement for fire prevention. Based on the reasons above mentioned, fire prevention codes applying to those in Taiwan are badly in need. U.S. Nuclear Regulatory Commission (USNRC) declared a new regulatory policy, permitting reactor licensees to voluntarily adopt a set of fire protection requirements contained in the National Fire Protection Association Standard 805, of fire protection programs for nuclear power plants. Such a new regulatory policy allows alternative method for early-existed NPPs to tally with the prescriptive requirements.
This research integrates regulations of NFPA 804 and 805, which contain hardware and software requirements. For increasing the practicability, the estimation lists were checked by personnel in charge of Nuclear Power Plant. Beside, the research simulates with fire dynamic simulator code to figure out the effect of sprinkler system on cable spreading room with shielding fire. The result shows that shielding fires delay the activation of sprinkler system and reduce its effect. Moreover, the effects vary mainly with operation pressure. The more operation pressure set in shielding fires, the more effect it could be. Key words: NFPA 805, Nuclear Power Plant, Cable Spreading Room
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Monideep K. D.1992. Evaluation of Fire Models for Nuclear Power Plant Applications: Cable Tray Fires, p6.
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http://vm.nthu.edu.tw/science/shows/nuclear/safety/content.html
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24119882
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http://www.libertytimes.com.tw/2004/new/aug/10/today-int1.htm
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http://www.nuce.boun.edu.tr/psaover.html
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http://www.libertytimes.com.tw/2004/new/aug/10/today-int1.htm
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Monideep K.D.NISTIR 6872, Evaluation of Fire Models for Nuclear Power Plant Applications: Cable Tray Fires, p9.
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Monideep K. Dey NISTIR 6872, Evaluation of Fire Models for Nuclear Power Plant Applications: Cable Tray Fires, p6.
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15m×10m×4.5m 150×100×45
50(m1/2/s1/2)
0.481.372.2(Bar)
740C 42(L/min/bar1/2)
800µm
10cm
1.72.1
15m×0.6m×0.1m
PVC 222kW/m2 2MW
(MW)
(m)
(Bar)
Case1 2 Case2 2 Case3 2 Case4 2 Case5 2 Case6 2 Case7 2 Case8 2 Case9 2 Case10 2 Case11 2 Case12 2
1.7 0.48 1.7 0.48 1.7 1.37 1.7 1.37 1.7 2.2 1.7 2.2 2.1 0.48 2.1 0.48 2.1 1.37 2.1 1.37 2.1 2.2 2.1 2.2 54
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(Shield
ing) (Bar)
0.48
1.7
1.37
2.2
0.48
2.1
1.37
2.2
350
400
252 254 353 22 277 282 431 70 252 254 352 5.7 280 284 422 10.7 252 254 353 0.95 280 284 425 0.6 256 272 371 1 270 285 423 252 255 265 362 14.2 270 275 411 60 256 261 361 1.85 272 273 407 2.
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