|
I
|
These
are
just
a
few
of
the
many
hundreds
of
thermal
hydraulic
computer
programs.
 |
While
these
are
publicly
available
Web
sites,
they
are
designed
for
users
with
advanced
technical
knowledge
of
NASA's
programs
and
related
fields.
|
| Network
Analysis
Inc.
-
Home
of
Sinda/G,
a
powerful
thermal
analysis
code
developed
originally
for
the
aerospace
industry. |
| Magsoft
-
Scientific
modelling
software
used
to
compute
electromagnetic,
thermal,
and
active
material
related
phenomena.
FEM/BEM
based
CAD
programs
for
2D/3D
analysis. |
Thermal
Hydraulic
codes
are
used
to
analyze
loss
of
coolant
accidents,
(LOCAs),
and
system
transients
in
light
water
nuclear
reactors.
These
thermal
hydraulic
codes
are:
- RELAP5
- Small
break
LOCA
and
system
transient
analysis
tool
for
PWRs
or
BWRs.
Capability
to
model
thermal
hydraulic
phenomena
in
1-D
components.
- TRAC-P
- Large
break
LOCA
and
system
transient
analysis
tool
for
PWRs.
Capability
to
model
thermal
hydraulic
phenomena
in
1-D
or
3-D
components.
- TRAC-B
- Large
and
small
break
LOCA
and
system
transient
analysis
tool
for
BWRs.
Capability
to
model
thermal
hydraulic
phenomena
in
1-D
or
3-D
components.
- TRAC-M
- Consolidation
and
modernization
of
TRAC-P
and
TRAC-B.
Resultant
code
will
be
able
to
analyze
large/small
break
LOCAs
and
system
transients
in
both
PWRs
and
BWRs.
Capability
to
model
thermal
hydraulic
phenomena
in
1-D
or
3-D
components.
- CONTAIN
- Containment
transient
analysis
tool
for
PWRs
or
BWRs.
Capability
to
model
thermal
hydraulic
phenomena
(within
a
lumped-parameter
framework)
for
existing
containment
designs.
SNAP
- Symbolic
Nuclear
Analysis
Package,
SNAP,
is
a
graphical
user
interface
currently
with
pre-processor
capabilities
that
assist
the
user
in
the
development
of
RELAP5
input
decks
and
in
running
the
code.
Future
improvements
include
a
post-processor
having
"simulator-like"
visualization
and
run-time
control
capabilities.
SNAP
is
also
being
extended
to
work
with
the
consolidated
TRAC
code
and
will
have
the
functionality
to
run
the
TRAC
code
using
RELAP5
input
decks.
| Calculations
and
equations
for
fluid
mechanics,
flow
measurement,
hydrology,
culverts,
channels,
orifices
LMNO
Engineering
website
has
interactive
calculations
with
equations
for
open
channels,
pipes,
culverts,
hydraulics,
hydrology,
groundwater,
runoff,
storage
tanks.
Water,
liquid,
gas
flow
rate
measurement
-
venturis,
orifices,
nozzles,
weirs. |
| Fluid
Dynamics:
Genesis,
Version
1.2
This
freeware
utility
allows
you
to
create
and
maintain
web
pages
from
the
convenience
of
your
web
browser.
|
| SYSTEM
ANALYSIS
Laboratory
for
Thermal
Hydraulics
(LTH)
MODELING
AND
ANALYSIS,
LWR
SAFETY
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. |
| AP
PIONEER
A
collection
of
programs,
each
optimized
to
a
...
ANALYZER
PROGRAM.
The
Thermal
Hydraulic
Analyzer
Program
(THAP)
is
a
digital
computer
program. |
| Safety
Research:
1979
-
present
Required
the
development
of
sophisticated
computer
programs
to
accurately
model
the
neutronic
and
thermal-hydraulic
behavior
these
highly
coupled
systems. |
| Reactor
Analysis:
Computer
Codes:
SAS-DIF3DK
Computer
Codes:
SAS-DIF3DK
SAS-DIF3DK
Standardized
Code
Description
Program
Name
and
Title
:
SAS-DIF3DK
Computer
for
Which
Program
is
Designed
and
Other
Machine
Version
Packages
Available
:
Mainframe
(IBM,
CRAY,
CDC,
etc.),
UNIX
Workstation
(SUN).
|
| Reactor
Analysis:
Computer
Codes:
SASSYS-1
Computer
Codes:
SASSYS-1
SASSYS-1
Standard
Code
Description
Name
of
Program
:
SASSYS-1
Computer
for
Which
Program
is
Designed
and
Other
Machine
Version
Packages
Available
:
Mainframe
(IBM,
CRAY,
CDC,
etc.),
Unix
Workstation
(Sun,
IBM
RISC,
HP,
SG),. |
| Reactor
Analysis:
Computer
Codes:
COMMIX-1AR/P
Computer
Codes:
COMMIX-1AR/P
COMMIX-1AR/P
Three-Dimensional
Thermal-Hydraulic
Analysis
Standardized
Code
Description
Program
Name
and
Title
:
COMMIX-1AR/P
Computer
for
Which
Program
Is
Designed
and
Other
Machine
Versions
Available
:
SUN
Microsystems. |
| NEA-1313:
BWRDYN,
Thermal
hydraulic
analysis
of
a
BWR
plant
NEA
Data
Bank
Program
Abstract:
NEA-1313:
BWRDYN.
12-JUN-1990
KWIC:
BWRDYN,
Thermal
hydraulic
analysis
of
a
BWR
plant
Abstract
Table
of
Contents.
| TPL:
Activities/Publications
Installations
:
Pulsed
Reactors
Coupled
Reactor
Systems
Reactor
Pumped
Lasers
Emerging
Nuclear
Energy
Systems
Publications
BARS-6
reactor
OKUYAN
system
Neutron
and
Particle
Transport
Reactor
Kinetics
and
Dynamics
Nuclear
Safety
Publications.
| NEA
Computer
Program
Services:
Material
Available
from
Us
Our
computer
program
collection
is
in
a
constant
state
of
evolution
and
adaptation
as
we
receive
new
material
and
update
and
test
existing
material.
Thus,
program
abstracts
available
on
the
Computer
Program
Abstracts.
| Reactor
Analysis:
Computer
Codes:
DIF3DK
Computer
Codes:
DIF3DK
DIF3DK
Standardized
Code
Description
Program
Name
and
Title
:
DIF3D-K
1.5:
A
Nodal
Kinetics
Code
for
Solving
the
Time-
Dependent
Diffusion
Equation.
Computer
for
Which
Program
is
Designed
and
Other
Machine
Versions
Available.
| Engineering
Mechanics
and
Thermal
Systems
Technology
Numerical
Heat
Transfer
Analysis
The
Thermal
Hydraulics
and
Energy
Storage
Group
and
the
Thermal
Analysis
Group
have
experience
with
a
wide
variety
of
numerical
techniques
for
solving
heat
transfer
problems.
The
engineers
in
both
groups
can
use.
| NEA-1305:
COOLOD,STEADY-STATE
THERMAL
HYDRAULICS
OF
RESEARCH
REACTORS
NEA
Data
Bank
Program
Abstract:
NEA-1305:
COOLOD.
16-OCT-1997
KWIC:
COOLOD,STEADY-STATE
THERMAL
HYDRAULICS
OF
RESEARCH
REACTORS.
| NEA-0100:
HYTHEST,DEPENDENCE
OF
FUEL
FABRICATION_TOLERANCES
ON
HYDRAULICS
OF
BWR,PWR
NEA
Data
Bank
Program
Abstract:
NEA-0100:
HYTHEST.
09-APR-1981
KWIC:
HYTHEST,DEPENDENCE
OF
FUEL
FABRICATION_TOLERANCES
ON
HYDRAULICS
OF
BWR,PWR
.
| Research
and
Development
The
Experimental
Thermal
Hydraulics
Research
Group
is
the
main
contributor
to
the
publicly
funded
Thermal
Hydraulic
Experiments
and
Analyses
(TEKOJA)
project
(1995-98),
a
part
of
the
Finnish
Research
Programme
on
Reactor
Safety.
| CTRS
Page
-
Facilities
Facilities
The
Center
has
two
dedicated
computing
facilities
equipped
with
5
Sun
and
DEC
ALPHA
workstations
and
15
top
of
the
line
PCs
with
a
dedicated
server.
In
addition,
the
computer
laboratory
of
the
Materials
and
Nuclear
Engineering
Department.
| Computer
Resource
Guide:
5.2
Computer
Resource
Guide
5.2
Supported
Programs
in
VMS
environment
The
nature
of
workstation
environment
dictates
that
software
support
is
arranged
through
the
system
manager.
The
following
list
indicates
the
supported
software.
| ANL
RE
Division:
Heat
Transfer
ANL
Reactor
Engineering
Division
Heat
Transfer
Expertise
The
Reactor
Engineering
division
has
wide-ranging
expertise,
experience,
and
accomplishments
in
the
field
of
heat
transfer
that
have
been
developed
in
support
of
reactor
safety.
|
| | | | | | | | | |
|
