MOX (Plutonium-Uranium mixed Oxide) Nuclear Fuel

AI Thread Summary
Japan has recently begun operating a MOX-fueled reactor, contributing to a projected global MOX fuel usage of about 5% this year. However, the accuracy of this figure is debated due to the limited number of facilities capable of producing MOX fuel and the typical loading practices in reactors. MOX fuel generally contains around 5-8% plutonium and is often used in mixed cores with uranium dioxide assemblies. Countries like France and Germany have established programs for MOX usage, while Japan's recent adoption marks a significant development. The discussion highlights the complexities and limitations surrounding MOX fuel deployment in nuclear power generation.
CFDFEAGURU
Messages
781
Reaction score
10
Hello all,

I just read an article in POWER magazine for this month (January 2010) that Japan is now operating a MOX-fueled reactor.

In this article it is stated that MOX-fuel usage should be about 5% globally this year. Is that statement accurate given the small number of facilites that can produce MOX fuel?

Thanks
Matt
 
Engineering news on Phys.org
CFDFEAGURU said:
In this article it is stated that MOX-fuel usage should be about 5% globally this year. Is that statement accurate given the small number of facilites that can produce MOX fuel?
The countries with lots of nuclear power (France and Japan) can run mox fuel in pretty much all of the plants, I think CANDUs can also run on MOX.
 
I don't believe the 5% figure is accurate.

MOX fuel is only about 5% Pu to begin with and the plants that do run it usually only load about a third of the core with it.

Are there any CANDU's on MOX?
 
It might be 5% of plants, but I'd have to read the article. MOX is usually loaded in mixed core with UO2 assemblies. A number of EU programs - primarily France and Germany are running MOX assemblies. Japan recently started MOX. MOX is typically 6-8% Pu to match the 4.0-5% U-235 equivalent. The commercial MOX uses LWR RG Pu and not WG-derived Pu.

CANDUs have historically used natural U in UO2, but CANFLEX assemblies have been using slightly enriched U more recently.
 
... but I'd have to read the article

Astronuc,

Here is a link to the magazine that contains the write up. It starts on page 8.

The title is "Japan Launches Commercial Operation of MOX-Fueled Reactor"

http://www.powermag-digital.com/powermag/201001_1#pg1

If you don't have an account, you'll have to create on, but it is free.

Thanks
Matt
 
Last edited by a moderator:
Hello everyone, I am currently working on a burnup calculation for a fuel assembly with repeated geometric structures using MCNP6. I have defined two materials (Material 1 and Material 2) which are actually the same material but located in different positions. However, after running the calculation with the BURN card, I am encountering an issue where all burnup information(power fraction(Initial input is 1,but output file is 0), burnup, mass, etc.) for Material 2 is zero, while Material 1...
Back
Top