Molten Salt [reactor] Coolants [pres. slides]

18 Pages·2003·0.775 MB·English

Molten Salt Coolants:
Transferring Heat From Reactors to H Facilities
2
The Advanced High-Temperature Reactor for H Production
2
Charles Forsberg (ORNL)
Paul Pickard (SNL)
Per Peterson (U.C.-Berkeley)
Oak Ridge National Laboratory
P.O. Box 2008; Oak Ridge, TN 37831-6179
Tel: [phone]; E-mail: [email protected]
DOE Nuclear Hydrogen Planning Meeting
Hilton Head, South Carolina
March 13, 2003
The submitted manuscript has been authored by a contractor of the U.S. Government under contract DE-AC05-00OR22725. Accordingly, the U.S. Government retains a nonexclusive, royalty-free license to publish or
reproduce the published form of this contribution, or allow others to do so, for U.S. Government purposes. File name: DOE.Hydrogen.HiltonHead.March13.2003
The Advanced High-Temperature Reactor
for Hydrogen Production
Passive Decay Reactor Hydrogen Production
Heat Removal Options
Molten Fluoride Salt
Oxygen Hydrogen
(Example: NaF/ZrF )
4
750o to 1000oC
Hot Air
Out
Control
Pump
Rods Thermochemical
Hot Electrolysis
Nuclear-Assisted
Air Inlet Cooling
Steam Reforming
Water
of Natural Gas
Fuel
Reactor Vessel
Radiation Heat Water
Transfer (Operates at
Higher Temperatures)
Guard Vessel
03-022
The AHTR Is NOT
a Molten Salt Reactor (MSR)
• MSR
− Fuel dissolved in the
Off-gas
System
molten salt
Separate Facility Primary Secondary
(Colocated Salt Pump NaBF4_NaF Salt Pump
or off-site) Coolant Salt
Converter (CR~0.9) − Aircraft Reactor
Waste Burner
Experiment operated at
Purified Electricity
Salt Graphite (Helium/Gas Turbine)
Moderator 815 °C
Heat
Exchanger or
Hydrogen • AHTR
Reactor (Thermochemical)
Fuel Salt
Freeze − Solid fuel
Plug
Coupled
to Reactor
− Molten salt coolant
Critically Safe, Passively Cooled
Breeder Dump Tanks (Emergency
Cooling and Shutdown)
− Uses MSR experience
The AHTR and VHTR Use the
Same Coated-Particle Fuel
Fuel Handling
Fuel Rod
Hole
Dowel Pin
Annular Coolant
Fuel Kernel Coated Channel
Fuel Plug
High Density PyC
Particle
Graphite
SiC
Fuel Block
Low Density PyC
Compact
Graphite
8 mm
Sleeve
0.92 mm
580 mm
39 mm
34 mm
Dowel Socket
26 mm
360 mm
Fuel Compact Fuel Rod Fuel Block
ORNL DWG 2001-45
AHTR Molten Salt Reactor Technology Was
Developed in the Aircraft Nuclear Propulsion
Program with Test Reactor Operations to 860°C
(Requirements: Low Pressure and Efficient Heat Transfer)
A Molten-Salt-Cooled Reactor Reduces Reactor
Temperatures Compared to Gas-Cooled Reactors
Bulk Coolant Temperature Rise Temperature Rise From Coolant
Across Reactor To Fuel Centerline
Reactor Coolant Reactor Nuclear Fuel
Entrance Coolant Exit Bulk Coolant Peak
Temperature Temperature Temperature Temperature
600° 600°

k
ant
ea 500° 500°
e P Pl ve ure
vn ot
oe ba
bg 400° Aer 400°
Ao
) dr C) mp
Cy
°e
re (°he H 300° ure (nt T 300° Helium
uT ta
ato Helium raol
erT 200° peCo 200°
pe m
mr k
u el
et Tu
Ta B
100° 100°
t er Molten Salt
np Molten Salt
am
l Temperature Of
o
e
o
T 0 Delivered Heat To 0
C
Hydrogen Plant
03-017
Power Reactor Experience Shows That Liquid
Coolants Minimize Peak Reactor Temperatures
1000
AHTR or MSR
1000°C
850°C 925°C
Hydrogen Production
800
750°C
AHTR or MSR
665°C
)
C
675°C
°
e ( 600 545°C HTGR-GT
r 491°C
u (General Atomics)
t
a
er LMFBR 395°C
p (Super Phenix)
m 400
e AGR 310°C
T 319°C (Hinkley Point B)
PWR 299°C
200 (Point Beach)
Liquid
Gas
0
Inlet Outlet
Delivered Heat
02-130
The AHTR Is the Child of GenIV:
It Was Developed in the GenIV Process and Combines GenIV Technologies
High-Temperature Molten Salt
Reactor Technology Reactor Technology
Fuel Coolant
Advanced High Temperature Reactor
Fusion (Molten
Molten Salt
Salt Cooling)
(Fueled) Reactor
03-040
There Is a Massive R&D Overlap Between
the AHTR and VHTR
Common R&D
• Nuclear Fuels
• Materials
• Hydrogen Production
AHTR VHTR
− Nuclear Assisted
Steam Reforming
− Thermochemical
03-016
Molten-Salt Heat Transfer Loops May Be Preferred To
Transfer Heat From a Reactor to the H Facilities
2
(German Studies Supported Molten Salt Coolant Between Gas-Cooled Reactors
and H Facilities; Molten Salts Used in the Chemical Industry)
2
Nuclear Safety by Isolation Hydrogen Safety by Dilution
Oxygen
Hot Air Out
Control
Rods
Molten Salt
H
2
Air
Inlet Water
Molten Salt
Heat-Transfer Loop
• High Heat Capacity
• Low Pumping Costs
• Low Pressure
• Industrial Experience
02-176