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I
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Nuclear
thermal
hydraulics
is
related
to
applied
research
on
a
variety
of
issues
related
to
nuclear
reactor
thermal-hydraulics
and
safety,
which
deal
with
energy
production
and
utilization.
Some
of
the
research
topics
may
include:
 | Single
and
two-phase
phenomena
in
heated
microchannels
(convective
heat
transfer,
boiling,
onset
of
flow
instability,
flow
regimes,
single
and
two-phase
pressure
drop);
|
| Single
and
two-phase
phenomena
in
tube
bundles
(flow
visualization,
two-phase
flow
patterns);
| Thermal-hydraulics
of
the
accelerator-based
production
of
tritium
(apt)
system;
| Enhancement
of
boiling
heat
transfer;
| Interphase
transfer
processes
in
two-phase
flow;
| Transport
of
radioactive
trace
species
and
aerosols
in
bubbles;
| Condensation
in
two-phase
flow
systems
with
noncondensables;
| Modeling
of
nonequilibrium
two-phase
mist
flow;
| Hydrodynamics
of
countercurrent
two-phase
flow;
| Hydrodynamics
of
three-phase
(gas-liquid-solid
particles)
flow
systems. |
| Numerical
modeling
of
condensation
with
noncondensables;
| Modeling
of
condensation
in
thermal-hydraulics
system
codes;
| Dynamic
testing
and
simulation
of
digital
feedwater
control
systems
in
BWR’s;
| Flow
visualization
and
particle
image
velocimetry
for
nonequilibrium
two-phase
flow;
| Development
of
in-line
moisture
fraction
measurement
instrumentation;
| Mechanistic
modeling
of
steam
explosions;
| Thermal-hydraulics
of
fuel
cells. |
| | | | | | | | | | | | | |
To
cover
this
area
is
certainly
an
immense
undertaking,
so
we
have
provided
some
information
and
links
below
that
will
help
you
to
get
started.
The
UCBNE
Thermal
Hydraulics
Research
Group.
Department
of
Nuclear
Engineering.
University
of
California
at
Berkeley.
Research.
|
Dr.
Richard
T.
Lahey
Nuc.
Sci.
&
Eng.,
88,
1984
and
2
nd
Proceedings
on
Nuclear
Thermal
Hydraulics,
Annual
Meeting
of
American
Nuclear
Society,
New
Orleans,
Louisiana,
1984.
|
Information
and
research
on
nuclear
thermal
hydraulics.
Fundamental
research
presented
in
fluid
dynamics.
Browse
the
index
of
articles.
| Reactor
Analysis:
Publications:
International
Nuclear
Safety
RA
Publications
-
International
Nuclear
Safety
International
Nuclear
Safety
Publications
List
of
Publications
"Computationally
Efficient
Thermal
Hydraulics
Calculations
in
the
SAS-DIF3DK
Coupled
Reactor
Physics
and
Thermal
Hydraulics
Code.
|
| Nuclear
Safety
Research
Center:
Current
Research
College
of
Engineering
University
of
Wisconsin
-
Madison
Nuclear
Safety
Research
Center
About
the
NSRC
Goals
Personnel
Current
Research
Facilities
Computer
Simulation
Models
Publications
Current
Research:
Thermal
Hydraulics
Influence
of
Solid
Fraction. |
Work
in
this
area
is
related
to
two-phase
flow
and
heat
transfer
problems
encountered
in
LWR
and
advanced
LWR
accident
analysis.
The
role
of
the
Modelling
and
Analysis
Group
is
to
support
both
the
nuclear
related
research
of
LTH
and
other
projects
within
the
Nuclear
Energy
and
Safety
Department
of
PSI.
Activities
include
experimental
and
analytical
research
of
fundamental
phenomena,
analysis
of
experimental
data,
analytical
model
development,
code
assessment,
and
services
to
the
Swiss
nuclear
power
plants
(NPP)
and
the
Swiss
Nuclear
Safety
Authority.
PACTEL
Group"
Experimental
Thermal
Hydraulics,
Nuclear
Energy,
VTT
Energy.
Nuclear
Engineering
Laboratory,
Department
of
Energy
Technology.
Recent
Work
by
the
Analytical
Thermal-Hydraulics
Section.
Publications.
Enhancement
and
Suppression
of
Turbulence
in
Particulate
Flow.
...
PIPESYS:
Pipeline
Thermal
&
Hydraulics
Extension.
Introduction
Capabilities
Technical
Features
PIPESYS
Advantage.
Analytical
Thermal-Hydraulics.
[Publications
|
Fact
Sheets]
Section
Manager:
R.
A.
Valentin
(Acting)
Staff:
M.
Bottoni,1
F.
C.
Chang.
Lectures
in
Thermal
Hydraulics
Considerations
in
the
Licensing
and
Safety
Analysis
of
Nuclear
Power
Reactors.
Gary
E.
Wilson.
INSTITUTE
OF
THERMAL-
HYDRAULICS.
Director:
Dr.
M.
Ishii
Sponsored
by:
US
Nuclear
Regulatory
Commission
Laboratory
and
School
Affiliation.
Thermal-hydraulic
characterization
of
high
heat
flux
components
for
fusion
reactors.
Activity
description.
Experimental
facility.
Thermal
Hydraulic
Resources
on
the
Web.
Thermal
Connection.
Fluid
Mechanics
Web
Server.
Applied
Thermal
&
Fluid
flow.
Program
Service
|
Recent
programs]
NEA
Data
Bank
Program
Abstract:
NESC1091:
COBRA-SFS.
14-DEC-1989
KWIC:
COBRA-SFS,THERMAL
HYDRAULICS
OF
SPENT
FUEL.
Structural
Mechanics
and
Thermal
Hydraulics.
People.
Dr.
Liping
Ni.
Projects.
Structure
mechanics
in
the
MEGAPIE
target.
W.
J.
Rider.
Advanced
Numerical
Techniques
for
Thermal-Hydraulics
Presented
at
the
National
Heat
Transfer
Conference
1993.
Thermal-Hydraulics
and
Safety.
Principal
Faculty:
S.
I.
Abdel-Khalik,
S.
M.
Ghiaasiaan,
S.
M.
Jeter
(ME),
and
M.
Yoda
(ME).
If
a
vacuum
vessel
(VV)
of
a
fusion
reactor
breaks,
an
external
fluid
may
flow
into
the
inside
of
the
VV
through
breaches.
In
the
International
Thermonuclear
Experimental
Reactor
(ITER)
design,
air
is
being
assumed
to
be
the
external
fluid.
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