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RELAP5/MOD3
is
a
computer
code
used
for
the
thermal-hydraulic
analysis
of
transients
and
small-break
type
accidents
in
light-water
nuclear
power
plants
by
the
Nuclear
Regulatory
Commission
(NRC).
It
uses
a
one-dimensional,
two-fluid
model,
consisting
of
steam
and
water,
with
the
possibility
of
the
vapor
phase
containing
a
noncondensible
component
and
the
liquid
phase
containing
a
nonvolatile
solute.
The
Office
of
Research
plans,
recommends,
and
implements
programs
of
nuclear
regulatory
research.
Independently
proposes
regulatory
outcomes
in
the
form
of
improvements
to
NRC's
regulatory
programs
to
achieve
enhanced
safety,
efficiency,
or
effectiveness.
Based
on
research
results
and
experience
gained,
resolves
safety
issues
for
nuclear
power
plants
and
other
facilities
regulated
by
the
NRC
including
those
issues
designated
as
Generic
Safety
Issues.
Conducts
research
to
reduce
uncertainties
in
areas
of
potentially
high
risk
or
safety
significance.
Leads
agency
initiative
for
cooperative
research
with
DOE,
the
nuclear
industry,
universities
and
international
partners.
Collects,
analyzes,
and
disseminates
operational
data;
assesses
trends
in
performance
from
this
data;
evaluates
operating
experience
to
provide
insights
into
and
improve
the
understanding
of,
the
risk
significance
of
events;
and
produces
periodic
performance
indicator
and
Accident
Sequence
Precursor
Reports.
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