Very high temperature reactor
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The Very High Temperature Reactor is a Generation IV reactor concept that uses a graphite-moderated nuclear reactor with a once-through uranium fuel cycle. This reactor design envisions an outlet temperature of 1000°C. The reactor core can be either a “prismatic block” or a “pebble-bed” core. The high temperatures enable applications such as process heat or hydrogen production via the thermo-chemical sulfur-iodine cycle.
The reactors are intended for use in nuclear power plants to produce nuclear power from nuclear fuel.
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[edit] History
This design was formerly known as "High Temperature Gas-cooled Reactor" or HTGR, originally developed in the 1950s by Professor Dr. Rudolf Schulten in Germany. The Fort St. Vrain Generating Station was one example of this design that operated as an HTGR from 1979 to 1989; though the reactor was beset by some problems which led to its decommissioning due to economic factors, it served as proof of the HTGR concept in the United States (though no new commercial HTGRs have been developed there since).[1] HTGRs have also existed in Germany, Japan and China, and are promoted in several countries by reactor designers.[2] More recently, this reactor design type has been updated and is now more commonly known as the Very High Temperature Reactor.
[edit] Nuclear reactor design
[edit] Neutron moderator
Some United States and Russian designs refer to a prismatic block core configuration, where hexagonal graphite blocks are stacked to fit in a circular pressure vessel. Pebble bed designs are also being studied and have been used at lower temperatures than those envisioned for the VHTR. Pebble bed designs usually have a core where the pebbles are in an annulus, and there is a graphite center spire.
[edit] Nuclear fuel
The fuel is usually referenced to be uranium dioxide in a TRISO configuration, however, uranium carbide or uranium oxycarbide are also possibilities. A combination of uranium dioxide and uranium carbide may also be used to reduce internal pressure in the TRISO particles caused by the formation of carbon monoxide, due to the oxidization of the porous carbon layer in the particle.[3] The TRISO particles are either dispersed in a pebble for the pebble bed design or molded into compacts/rods that are then inserted into the hexagonal graphite blocks. The QUADRISO fuel concept conceived at Argonne National Laboratory has been used to better manage the excess of reactivity.[4]
[edit] Coolant
[edit] Helium
This helium cooled reactor type is the dominant one being studied; its primary design uses a 600-MW thermal core with a helium outlet temperature of 1,000°C. Helium has been used in most high temperature gas reactors (HTGR) to date. Helium is an inert gas, so it will not chemically react with any material.[5] Additionally, exposing helium to radiation does not make it radioactive[6], unlike most other possible coolants.
[edit] Molten salt
The molten salt cooled variant, the LS-VHTR, similar to the advanced high temperature reactor (AHTR) design, uses a liquid fluoride salt for cooling in a pebble core. It shares many features with a standard VHTR design, but uses molten salt as a coolant instead of helium. The pebble fuel floats in the salt, and thus pebbles are injected into the coolant flow to be carried to the bottom of the pebble bed, and are removed from the top of the bed for recirculation. The LS-VHTR has many attractive features, including: the ability to work at high temperatures (the boiling point of most molten salts being considered are >1,400°C), low pressure operation, high power density, better electric conversion efficiency than a helium-cooled VHTR operating at similar conditions, passive safety systems, and better retention of fission products in case an accident occurred.
[edit] Control
In the prismatic designs, control rods would be inserted in holes cut in the graphite blocks that make up the core. The VHTR will be controlled like current PBMR designs if it utilizes a pebble bed core, the control rods will be inserted in the surrounding graphite reflector. Control can also be attained by adding pebbles containing neutron absorbers.
[edit] Materials Challenges
The high temperature, high neutron dose, and corrosive operating conditions of the VHTR require materials that exceed the limitations of current nuclear reactors. Materials that have high dimensional stability, either with or without stress, maintain their tensile strength, ductility, creep resistance, etc after ageing, and are corrosion resistant are primary candidates for use in VHTRs. Some materials suggested include nickel-base superalloys, silicon carbide, specific grades of graphite, high chromium steels, and refractory alloys.[7]
[edit] Safety features and other benefits
The design takes advantage of the inherent safety characteristics of a helium-cooled, graphite-moderated core with specific design optimizations. The graphite has large thermal inertia and the helium coolant is single phase, inert, and has no reactivity effects. The core is composed of graphite, has a high heat capacity and structural stability even at high temperatures. The fuel is coated uranium-oxycarbide which permits high burn-up (approaching 200 GWd/t) and retains fission products. The high average core-exit temperature of the VHTR (1,000°C) permits emissions-free production of process heat.
[edit] References
- ^ IAEA HTGR Knowledge Base
- ^ HTGR - High Temperature Gas-cooled Reactor _ Nuclear Pictures - NukeWorker.com
- ^ D. Olander J. Nucl. Mater. 389 (2009) 1-22.
- ^ Technical Articles on QUADRISO Fuel
- ^ "High temperature gas cool reactor technology development" (PDF). IAEA. 1996-11-15. pp.61. http://www.iaea.org/inisnkm/nkm/aws/htgr/fulltext/29026666.pdf. Retrieved on 2009-05-08.
- ^ "Thermal performance and flow instabilities in a multi-channel, helium-cooled, porous metal divertor module". Inist. 2000. http://cat.inist.fr/?aModele=afficheN&cpsidt=849696. Retrieved on 2009-5-8.
- ^ K.L. Murty, I. Charit, J. Nucl. Mater. 383 (2008) 189-195.
- Idaho National Lab VHTR website
- VHTR presentation
- Generation IV International Forum VHTR website
- INL VHTR workshop summary
- The European VHTR research & development programme: RAPHAEL
- Pebble Bed Advanced High Temperature Reactor (PB-AHTR)
[edit] See also
- TINTE
- Generation IV reactor
- Pebble bed reactor
- HTTR
- List of nuclear reactors
- Next Generation Nuclear Plant
- Nuclear physics
- Nuclear reactor physics
- UHTREX
[edit] External links
- IAEA HTGR Knowledge Base
- ORNL NGNP page
- INL Thermal-Hydraulic Analyses of the LS-VHTR
- Alberto Talamo Technical Articles
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