Quick one about first steps in mathematical modelling of nuclear stuff

AI Thread Summary
For those interested in modeling nuclear power, several key aspects can be explored, including heat generation, neutron flux, radiation, fuel, and coolant flow. A recommended resource is the webKORIGEN module from Nucleonica, which offers a web-based application for burnup and depletion calculations in nuclear reactors. This tool allows users to conduct reactor simulations quickly and efficiently, supporting standardized problems for Pressurized Water Reactors (PWR), Boiling Water Reactors (BWR), and future technologies like the European Fast Reactor (EFR). The application aims to streamline the processes of input preparation, simulation execution, and graphical output generation. This could serve as a valuable starting point for anyone looking to model nuclear systems.
Azuma
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Hi,
I am looking to get some good information sources on modelling nuclear power in power plants and related fields. Anyone got any good starting points ?

P.S. I am a biomedical engineer looking into different fields.
 
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What aspect are you interested in trying to model?

Heat generation? Neutron flux? Radiation? Fuel? Coolant flow? What scale & accuracy are you interested in?
 
We have developed a web-based application for so-called burnup and depletion calculations in nuclear reactors. This is the webKORIGEN module in Nucleonica (www.nucleonica.net). You will have to register but access is free. With this simulation tool, you can be doing reactor simulations literally within minutes.

Our objective in this development was to facilitate the input preparation, pre-processing, running, post-processing and to offer a fast graphical output generation for webKORIGEN users. WebKORIGEN supports calculations for a set of standardized problems, trimmed to three major classes of nuclear plants. The nuclear systems supported by webKORIGEN are: the thermal power plants deployed worldwide as Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR) and a future extension to the current industrial technology : the European Fast Reactor (EFR).

Maybe this is the tool you are looking for.
 
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...
Hi everyone, I'm a complete beginner with MCNP and trying to learn how to perform burnup calculations. Right now, I'm feeling a bit lost and not sure where to start. I found the OECD-NEA Burnup Credit Calculational Criticality Benchmark (Phase I-B) and was wondering if anyone has worked through this specific benchmark using MCNP6? If so, would you be willing to share your MCNP input file for it? Seeing an actual working example would be incredibly helpful for my learning. I'd be really...
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