Approximate mass of special alloys in a nuclear reactor?

In summary, the total mass of materials contained in a typical Gen III or III+ PWR can vary depending on the specific reactor design. However, based on information from suppliers, the fuel cladding and other assembly components (Zr alloy), control rods (Ag-In-Cd alloy), and burnable neutron absorber (Gd) are mainly contained in the core. The fuel assembly also includes various structural grids made of Ni-based alloys and Zr alloy. The total mass of these materials can be estimated from the length of the control rod fingers/rodlets. Other sections of the design document may provide information on the mass of Inconel and stainless steel used in the steam generators and piping. Overall, there is no typical Gen III
  • #1
uraninite
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Approximately, what is the total mass of these materials that is contained in a "typical" Gen III or III+ PWR (e.g., EPR, AP1000...)?

1/ Zr alloy (fuel cladding and other assembly components)?
2/ Ag-In-Cd alloy (control rods)?
3/ Gd (burnable neutron absorber)?
4/ Ni-based alloys?
5/ Stainless steel?

As this is quite a complicated question, please don't hesitate to only answer some parts of it. Thank you!
 
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  • #2
In the whole plant? All primary systems? The reactor vessel? Or just the fuel assemblies?
 
  • #3
My question is about the whole plant. However I would just need an order of magnitude and I guess that 1/ Zr alloy, 2/ Ag-In-Cd alloy and 3/ Gd are mainly contained in the core.
 
  • #4
One can find some numbers in the suppliers DCD for each reactor.

AP1000 - http://www.nrc.gov/reactors/new-reactors/design-cert/ap1000/dcd/Tier 2/Chapter 4/4-1_r14.pdf

The mass of cladding (ZIRLO) is 43,105 lb = 19,550 kg. Westinghouse fuel does not necessarily uses Gd as a burnable absorber, but rather ZrB2 coated on the fuel pellets. The fuel assembly has 10 structural spacer grids, including top and bottom (2) Ni-Cr-Fe Alloy 718 grids and 8 ZIRLO grids, and 4 intermediate (smaller) ZIRLO mid-span mixing grids.

The unit uses 53 RCCAs and 16 GRCAs. One can estimate the AIG and SS by the length of the fingers/rodlets. I believe other sections of Chapter 4 describe some of the ex-core systems, e.g., control rod drive mechanism.

There really is no typical Gen III+ reactor.

Other chapters probably have the masses of Inconel (typ 690) in the steam generators and stainless steel in piping. Stainless steel is typically 304/304L or 316/316L.
 
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  • #5
Thank you for these information.
 

What is the approximate mass of special alloys used in a nuclear reactor?

The approximate mass of special alloys used in a nuclear reactor varies depending on the type and size of the reactor. Generally, these alloys make up a small percentage of the overall mass of the reactor, with the majority being composed of materials such as concrete and steel.

What are some examples of special alloys used in nuclear reactors?

Some examples of special alloys used in nuclear reactors include zirconium alloys, which are used in fuel cladding, and stainless steel alloys, which are used for structural components. Other commonly used alloys include nickel-based alloys and titanium-based alloys.

Why are special alloys used in nuclear reactors?

Special alloys are used in nuclear reactors because they have properties that make them well-suited for the harsh conditions present in a nuclear reactor. These properties include high strength, corrosion resistance, and the ability to withstand high temperatures and radiation exposure.

How are the approximate masses of special alloys calculated for a nuclear reactor?

The approximate masses of special alloys in a nuclear reactor are calculated by taking into account the design and specifications of the reactor, as well as the types and amounts of alloys used in various components. These calculations are typically done during the design phase of a nuclear reactor.

What safety considerations are taken into account when selecting special alloys for a nuclear reactor?

When selecting special alloys for a nuclear reactor, safety is a top priority. The alloys must be able to withstand the extreme conditions within the reactor without degrading or causing any safety hazards. Extensive testing and quality control measures are taken to ensure the safety and reliability of these alloys in a nuclear reactor.

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