Graphite as a moderator in MSR and VHTR

In summary: Thank you for your interest in this topic.In summary, in Gen 4 reactors, graphite is used as a moderator due to its lower absorption cross section compared to water. Although more graphite is needed, the design of these reactors allows for sufficient space and flexibility. Other factors such as physical compatibility and cost also play a role in the choice of moderator.
  • #1
oksuz_
70
3
Hi,

In Gen 4 reactors, graphite is used as a moderator instead of water. Is it because of water's absorption cross section is higher than that of graphite? But as far as I know, you would need more graphite to thermalize neutrons. That is because water is commonly used in nuclear reactors. Is room not a problem in these type of reactors? thank you in advance.
 
Engineering news on Phys.org
  • #2
There are many different kinds of moderators that can be used.

The first thing to consider is probably that the moderator has the right physical characteristics to be compatible with the system. Graphite works will in MSRs and VHTR because it can withstand high temperatures and is compatible with the coolant (molten salt and gas). For example, the pressure of water and D2O would be very high at these temperatures.

The second thing to look at is probably cost. Graphite is relatively cheap compared to something like Beryllium.

Finally, if you just want the most effective moderator, there are three things to look at. (1) You want a small atomic mass so that the neutron loses the most energy per collision. In this regard, hydrogen is the best because it has the smallest atomic mass. (2) You want a moderator with a high macroscopic scattering cross section. You can have a high energy loss per collision, but it won't do any good if the scattering cross section is low. (3) Finally, you want a moderator with a low macroscopic absorption cross section. In this regard, deuterium has the lowest absorption. If you put these three things together, you can define a "moderating ratio" for different types of moderators. A list of moderating ratios is shown below:

* H2O 71
* D2O 5670
* He 83
* Be 143
* C 129
* Na-23 0.725
* U-238 0.0092

From this list, D2O is the most effective moderator. However, D2O doesn't have the right physical characteristics to work in a high temperature reactor.
Carbon/graphite has the third highest moderating ratio from the list above, it works at high temperatures, and is relatively inexpensive.

(See most reactor physics textbooks, such as Duderstadt and Hamilton, for a more detailed explanation.)
 
  • #3


Hi there,

Yes, you are correct. The reason why graphite is used as a moderator in Gen 4 reactors is because it has a lower absorption cross section compared to water. This means that it is better at slowing down neutrons without absorbing them, which is essential for maintaining a sustainable nuclear reaction.

As for the amount of graphite needed, it is true that more graphite is required compared to water. However, this is not a problem as the design of Gen 4 reactors allows for more space and flexibility in the use of materials. This means that there is enough room to accommodate the necessary amount of graphite without any issues.

I hope this helps to answer your question. Let me know if you have any further queries.
 

1. What is graphite and how is it used as a moderator in MSR and VHTR?

Graphite is a form of carbon that is commonly used as a moderator in nuclear reactors. In MSR (Molten Salt Reactor) and VHTR (Very High Temperature Reactor) designs, graphite is used to slow down the fast neutrons produced by the fission process, allowing them to interact with the fuel and sustain a chain reaction.

2. What are the advantages of using graphite as a moderator in MSR and VHTR?

Graphite has several advantages as a moderator in MSR and VHTR. It has a high melting point, making it suitable for use in high temperature reactors. It is also chemically stable and does not react with the molten salt or high temperature gas used as coolants in these reactors. Additionally, graphite has a low neutron absorption rate, allowing for a higher efficiency of the reactor.

3. Are there any disadvantages to using graphite as a moderator in MSR and VHTR?

While there are many advantages to using graphite as a moderator, there are also some potential disadvantages. Graphite can be prone to oxidation at high temperatures, which can lead to the release of carbon dioxide gas. It can also experience structural changes over time due to irradiation, which may require maintenance or replacement of the graphite components in the reactor.

4. How is the graphite used in MSR and VHTR reactors different from traditional nuclear reactors?

The graphite used in MSR and VHTR reactors is generally of a higher purity and density compared to that used in traditional nuclear reactors. This is to ensure that the graphite can withstand the high temperatures and corrosive environments present in these reactors. Additionally, the graphite in these reactors is often in the form of pebbles or spheres, rather than a solid block, to allow for better heat transfer and more efficient use of the moderator.

5. Can graphite be replaced with other materials as a moderator in MSR and VHTR?

While graphite is the most commonly used moderator in MSR and VHTR reactors, there are ongoing research and development efforts to explore alternative materials. Some potential replacements being studied include beryllium, zirconium hydride, and heavy water. These materials may offer different advantages and disadvantages compared to graphite, and further research is needed to determine their feasibility and effectiveness in these types of reactors.

Similar threads

  • Nuclear Engineering
Replies
2
Views
1K
Replies
6
Views
422
  • Nuclear Engineering
Replies
6
Views
2K
Replies
4
Views
4K
  • Nuclear Engineering
Replies
9
Views
2K
Replies
6
Views
240
Replies
3
Views
2K
  • Nuclear Engineering
Replies
4
Views
2K
Replies
5
Views
801
Replies
11
Views
2K
Back
Top