vifteovn said:I have visited the notebook forum, but the Triton section has not had a new post in over two years, so I'm not sure if is still active.
I want to determine the activity of mo-99 in uranium targets surrounding a reactor core. But I'm unsure what input parameters to choose for the burn-up scheme. I'm not sure what to choose power depletion or flux depletion, or if they are normalised or not.
The second issue how to determine the neutron flux in the core. Triton gives the average flux of the core, and is thus not that helpful in determining the best positions for the uranium targets.
When calculating the flux in KENO do you mean by the help of KMART?QuantumPion said:TRITON calculates spatially dependent fluxes using KENO or NEWT to pass to ORIGEN-S. To determine the best location to place the target, it would be simpler to create a plain KENO or NEWT model first since the TRITON output can become incomprehensibly lengthy.
The difference between the depletion modes is described in the Depletion Block section of the SCALE TRITON manual. The part that is normalized is the determination of total power which is used to calculate local fluxes. If you specify an average assembly power, the local flux is normalized. If you want to specify the flux or power of an individual pin, then the assembly power is normalized to the flux you specify.
vifteovn said:When calculating the flux in KENO do you mean by the help of KMART?
I tried to use NEWT, but it was not happy when I tried to run the model with 150 fuel assemblies, and it crashed.. Seems I can only make NEWT work with one-few fuel bundles, and that does not exactly help me place targets..
vifteovn said:Don't you need the whole core to get the correct flux?
Is there a way to get the outputfile to read neutrons/cm^2 s or will it only give up the relative flux?
The Triton Depletion Code for SCALE is a software tool used in the field of nuclear engineering to solve issues related to reactor core activity. It is part of the SCALE (Standardized Computer Analysis for Licensing Evaluation) software package, which is widely used in the nuclear industry for nuclear criticality safety and radiation shielding calculations.
The Triton Depletion Code for SCALE utilizes a detailed depletion analysis methodology to calculate the time-dependent isotopic composition of a nuclear reactor fuel assembly. It takes into account various factors such as fuel depletion, burnup, and fission product buildup, as well as the effects of neutron irradiation and decay on the isotopic composition of the fuel.
The Triton Depletion Code for SCALE is primarily used for reactor core design and analysis, fuel management, and nuclear fuel cycle analysis. It can also be used to study the effects of different operating conditions on the fuel cycle and to evaluate the potential for nuclear material proliferation in nuclear facilities.
The Triton Depletion Code for SCALE offers several advantages over traditional methods of depletion analysis. It is user-friendly, efficient, and accurate, and it can handle complex geometries and materials. It also has the ability to perform sensitivity and uncertainty analyses, which can help improve the safety and reliability of nuclear systems.
Yes, the Triton Depletion Code for SCALE is one of the most widely used depletion analysis tools in the nuclear industry. It is used by nuclear power plants, research institutions, and regulatory agencies around the world for various applications related to nuclear fuel and reactor core analysis.