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Nuclear Power Plant Design and Seismic Safety Considerations (Paperback)
Loot Price: R349
Discovery Miles 3 490
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Nuclear Power Plant Design and Seismic Safety Considerations (Paperback)
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Loot Price R349
Discovery Miles 3 490
Expected to ship within 10 - 15 working days
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The earthquake and subsequent tsunami that devastated Japan's
Fukushima Daiichi nuclear power station and the earthquake that
forced the North Anna, VA, nuclear power plant's temporary shutdown
have focused attention on the seismic criteria applied to siting
and designing commercial nuclear power plants. Some Members of
Congress have questioned whether U.S nuclear plants are more
vulnerable to seismic threats than previously assessed,
particularly given the Nuclear Regulatory Commission's (NRC's)
ongoing reassessment of seismic risks at certain plant sites. The
design and operation of commercial nuclear power plants operating
in the United States vary considerably because most were
custom-designed and custom-built. Boiling water reactors (BWRs)
directly generate steam inside the reactor vessel. Pressurized
water reactors (PWRs) use heat exchangers to convert the heat
generated by the reactor core into steam outside of the reactor
vessel. U.S. utilities currently operate 104 nuclear power reactors
at 65 sites in 31 states; 69 are PWR designs and the 35 are BWR
designs. One of the most severe operating conditions a reactor may
face is a loss of coolant accident (LOCA), which can lead to a
reactor core meltdown. The emergency core cooling system (ECCS)
provides core cooling to minimize fuel damage by injecting large
amounts of cool water containing boron (borated water slows the
fission process) into the reactor coolant system following a pipe
rupture or other water loss. The ECCS must be sized to provide
adequate makeup water to compensate for a break of the largest
diameter pipe in the primary system (i.e., the socalled
"double-ended guillotine break" (DEGB)). The NRC considers the DEGB
to be an extremely unlikely event; however, even unlikely events
can occur, as the magnitude 9.0 earthquake and resulting tsunami
that struck Fukushima Daiichi proves. U.S. nuclear power plants
designed in the 1960s and 1970s used a deterministic statistical
approach to addressing the risk of damage from shaking caused by a
large earthquake (termed Deterministic Seismic Hazard Analysis, or
DSHA). Since then, engineers have adopted a more comprehensive
approach to design known as Probabilistic Seismic Hazard Analysis
(PSHA). PSHA estimates the likelihood that various levels of ground
motion will be exceeded at a given location in a given future time
period. New nuclear plant designs will apply PSHA. In 2008, the U.S
Geological Survey (USGS) updated the National Seismic Hazard Maps
(NSHM) that were last revised in 2002. USGS notes that the 2008
hazard maps differ significantly from the 2002 maps in many parts
of the United States, and generally show 10%-15% reductions in
spectral and peak ground acceleration across much of the Central
and Eastern United States (CEUS), and about 10% reductions for
spectral and peak horizontal ground acceleration in the Western
United States (WUS). Spectral acceleration refers to ground motion
over a range, or spectra, of frequencies. Seismic hazards are
greatest in the WUS, particularly in California, Oregon, and
Washington, as well as Alaska and Hawaii. In 2010, the NRC examined
the implications of the updated NSHM for nuclear power plants
operating in the CEUS, and concluded that NSHM data suggest that
the probability for earthquake ground motions may be above the
seismic design basis for some nuclear plants in the CEUS. In late
March 2011, NRC announced that it had identified 27 nuclear
reactors operating in the CEUS that would receive priority
earthquake safety reviews.
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