Explore Alternative Transient Analysis Codes for Neutronic Operations

AI Thread Summary
The discussion focuses on the search for alternative transient analysis codes for neutronic operations, specifically comparing them to the S3K code currently in use. The ARROTTA code, developed by EPRI, is highlighted as a potential alternative, particularly when coupled with VIPRE-2, though its performance relative to S3K remains uncertain. Participants mention that many vendors use proprietary codes, limiting access to comparative information. Additionally, APROS, developed by VTT and Fortum, and PARCS from Purdue University are noted as other options worth exploring. Overall, there is a need for benchmark test results to facilitate a comparison among these codes.
MajestikMoose
Messages
5
Reaction score
0
At the moment I'n involved with a project that is using the S3K transient analysis code. I was wondering if anyone knows of a different code that will perform transient neutronic operations.

Thanks in advance
 
Engineering news on Phys.org
EPRI developed the ARROTTA code - 3D space-time kinetics code - for the purpose of reactor transient analysis. ARROTTA has been coupled with VIPRE-2. I don't know how well it performs with respect to S3K which is a fairly good code. The vendors have their own methods, but I believe they are not as advanced as S3K.

This paper might be useful - Parallel Computing Methods For The Epri Spatial Kinetics Code Arrotta
http://citeseer.ist.psu.edu/54277.html - look for options on the righthand side of the page for downloading.
 
Last edited:
Thanks. I know that a lot of vendors use their own 'in-house' codes and don't distribute them commercially but is there any way of getting more information about them for a comparison to S3K? I'm trying to compare to see how they stand up to each other. Any type of benchmark test results would be useful.
 
VTT and Fortum (Finland) have developed APROS, but I don't know much about it.
http://www.fortum.com/document.asp?path=14022;14024;14025;14035;15386;15387;15267;15273

There is a group in the Dept. of Nuclear Engineering at Purdue, who have developed PARCS, Purdue Advanced Reactor Core Simulator, which might be available.
https://engineering.purdue.edu/PARCS


Vendor methods are proprietary (trade secret) and the details are not available in the public domain.
 
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...
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...
Back
Top