Seeking examples reliably safe fission reactor designs

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The discussion focuses on the safety and design of fission reactors, particularly thorium reactors, which are noted for their high thermal conductivity and potential for passive safety features. Key points include the importance of cooling systems to prevent meltdowns, with the ESBWR design highlighted for its ability to maintain core cooling for 72 hours without power. Sealed, passive reactor designs are considered inherently safe due to their temperature feedback control mechanisms. Liquid nuclear fuel designs, while not widely implemented, operate in a way that allows for safe cooling through fail-safe mechanisms. Overall, the conversation emphasizes the need for reliable safety measures in nuclear reactor design to mitigate risks associated with coolant loss and heat management.
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What are some reliably safe designs for fission reactors? I'm particularly interested in thorium reactors as they cannot melt down1.

1http://www.physorg.com/news/2011-06-pint-sized-particle-nuclear-energy.html
 
Engineering news on Phys.org
The article in Physorg is about accelerator driven systems.

As for melting, thorium reactors certainly could meltdown.

Any fission system produces fission products, and fission products generate decay heat. If the heat is not removed via a cooling system, then the fuel material will melt.

Coolability is an inherent part of a reactor design. Some designs however can tolerate higher temperatures, e.g., reactor using TRISO fuel (with alternate layers of pyrolytic carbon and SiC or ZrC) in gas cooled environment driving a Brayton cycle. Thermal efficiencies increase with temperature, but then so does materials degradation in an irradiation environment or high temperature water/steam.

Thoria is desirable for its high thermal conductivity and higher melting point than UO2, although thoria systems would contain U-235, Pu-239 or U-233 which are fissile.

Accelerator driven systems could in theory produce fast neutrons for fission U-238 or Th-232, but also transmute longer-lived fission products to shorter-lived fission products. The feasibility however is yet to be determined.
 
The ESBWR design utilizes natural circulation and large accumulators, giving it 100% passive 72 hour safety capability, even under station blackout conditions.

There are also designs for sealed, passive reactors which use temperature feedback for control, which is also inherently safe.
 
treehouse said:
... I'm particularly interested in thorium reactors as they cannot melt down1.
There are liquid nuclear fuel designs, but no working implementations aside from a couple experimental reactors in the 1950s and 60s. In other words they operate in an 'already melted' state. Should the primary cooling mechanism of such a reactor stop or fail for some reason so that the fluid temperature continues to rise, the reactor releases the hot fluid by means of melting a fail safe freeze plug and then into a dump tank where the fluid can cool down safely. The dump tanks and freeze plug are shown in blue in this diagram:
http://upload.wikimedia.org/wikipedia/commons/0/08/Molten_Salt_Reactor.svg
 
QuantumPion said:
The ESBWR design utilizes natural circulation and large accumulators, giving it 100% passive 72 hour safety capability, even under station blackout conditions.

There are also designs for sealed, passive reactors which use temperature feedback for control, which is also inherently safe.

The sealed reactor designs sound safest as that suggests to me they don't leak radionuclides. Please tell me more about this.
 
QuantumPion said:
The ESBWR design utilizes natural circulation and large accumulators, giving it 100% passive 72 hour safety capability, even under station blackout conditions.

There are also designs for sealed, passive reactors which use temperature feedback for control, which is also inherently safe.

mheslep said:
There are liquid nuclear fuel designs, but no working implementations aside from a couple experimental reactors in the 1950s and 60s. In other words they operate in an 'already melted' state. Should the primary cooling mechanism of such a reactor stop or fail for some reason so that the fluid temperature continues to rise, the reactor releases the hot fluid by means of melting a fail safe freeze plug and then into a dump tank where the fluid can cool down safely. The dump tanks and freeze plug are shown in blue in this diagram:
http://upload.wikimedia.org/wikipedia/commons/0/08/Molten_Salt_Reactor.svg

Why are those reactor designs so safe? I need to express this as clearly as possible.

I'm thinking if current radionuclide storage techniques contain nearly all the hazardous materials, overscaling the thickness of the containment material will eliminate risks posed to humans by such.
 
QuantumPion said:
The ESBWR design utilizes natural circulation and large accumulators, giving it 100% passive 72 hour safety capability, even under station blackout conditions.

There are also designs for sealed, passive reactors which use temperature feedback for control, which is also inherently safe.

I need the math on how fast dangerous measurements can rise and the relative speed with which they can be brought under control.
 
treehouse said:
I need the math on how fast dangerous measurements can rise and the relative speed with which they can be brought under control.

Best information I have seen for ESBWR is the design certification descriptions at
http://www.nrc.gov/reactors/new-reactors/design-cert/esbwr.html. NRC site has other design certifications for AP1000 (in progress), ABWR and is in the process of reviewing others.

Math may be limited as much of the detailed design is considered proprietary. But if you need that level of information you probably need to team up with some technical experts to summarize the technical work. Even then, for the number of different designs, that could fill volumes.
 
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treehouse said:
Why are those reactor designs so safe? I need to express this as clearly as possible.

I'm thinking if current radionuclide storage techniques contain nearly all the hazardous materials, overscaling the thickness of the containment material will eliminate risks posed to humans by such.

The greatest risk factors for current commercial nuclear power plants is loss of coolant (e.g. by piping break) or loss of heat sink (e.g. by loss of feedwater flow due to station blackout). Since the ESBWR is designed to be cooled by natural circulation, even a total loss of power would not prevent the core from being cooled. Furthermore, the large accumulators allows the core to continue to be cooled by passive/gravity driven systems which do not require operator intervention or power to operate valves/etc for 72 hours, and minimal intervention allowing indefinite passive cooling.

The sealed reactors are small and therefore do not rely on active cooling to prevent damage, and are further protected by inherent nuclear design which precludes the possibility of a power excursion.
 
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