Blogs about: Mcnp

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Monte Carlo N-Particle Transport Code (MCNP)

minortfugm wrote 2 months ago: courtesy of IMSR by Hudan Kali ini MiNOR mau bahas sekilas mengenai salah satu software nuklir yang … more →

Tags: Monte Carlo (MCNP), Neutronics, Theory, Core, Criticality, Monte Carlo, neutronik, Nuclear, Nuklir

Additional EA added

gatornuke wrote 2 years ago: I’ve added an additional EA to the fray.  This one uses MACD states to define the market state … more →

Tags: MCNP_EA, Forex, Forex MCNP_EA, Programming, Monte Carlo

Metrics for the week

gatornuke wrote 2 years ago: This is the breakdown for the week for each EA tested.  Each trade was placed with 0.1 lots on the E … more →

Tags: MCNP_EA, Forex, Forex MCNP_EA, Programming, Monte Carlo

almost there

gatornuke wrote 2 years ago: Ok, we’re almost ready to start forward testing. I think the rest of my backtests should be do … more →

Tags: MCNP_EA, Forex

Serpent-to-MCNP input file converter

Andrei wrote 2 years ago: Serpent is a great user-friendly MC neutron transport code, which helps to calculate many characteri … more →

Tags: Monte Carlo, Software, Workflow, Ruby, serpent, input files, Converter

Finding all MCNP input cells with certain materials

Andrei wrote 2 years ago: After a Serpent input has been converted into MCNP format, one typically needs to add tallies in ord … more →

Tags: Programming, Monte Carlo, Software, Ruby, input files

3D-visualization of MCNP and Serpent models1 comment

Andrei wrote 2 years ago: At some point of reactor design development, there is a need to present the model to other people. 2 … more →

Tags: Software, Workflow, serpent, visualization

Using templates for making MCNP and Serpent input files4 comments

Andrei wrote 2 years ago: Computer codes for reactor core modeling, such as MCNP and Serpent, allow to define various geometri … more →

Tags: Monte Carlo, Software, Workflow, Ruby, Core Design, serpent, input files

Calculation of power peaking factor

Andrei wrote 2 years ago: In order to calculate the power peaking factor for my ADS model, I have slightly modified F17 tally … more →

Tags: Monte Carlo, Matlab, Core Design

Detailed visualization of power distribution in reactor core1 comment

Andrei wrote 2 years ago: A few days ago, I used MCNPX Mesh Tally to study power distribution in an ADS core. That approach is … more →

Tags: Programming, Monte Carlo, Matlab, serpent, visualization

Ocasional art

Andrei wrote 2 years ago: From time to time, every reactor physicist makes art. This particular piece was produced by incorrec … more →

Tags: Art, Matlab, Core Design, art 2

Print hierarchy of MCNP input cells and universes

Andrei wrote 2 years ago: Converting Serpent input to MCNP one, some additional cells have to be created to describe LAT and N … more →

Tags: Software, Workflow, Ruby, serpent, input files

Analyzing performance of MCNP calculations

Andrei wrote 2 years ago: We had some unexpected behavior of our cluster, and therefore I needed to analyze computing performa … more →

Tags: Monte Carlo, cluster computing, Software, Ruby, Performance

Optimization of fuel zones using MCNPX Mesh Tally1 comment

Andrei wrote 2 years ago: In order to minimize power peaking in ADS core, the core is divided into several zones with differen … more →

Tags: Monte Carlo, Matlab, Core Design

Aplikasi ENDF2ACE

dandiwijaya wrote 2 years ago: PENGEMBANGAN ANTARMUKA KONVERSI FILE DATA NUKLIR TEREVALUASI PADA RENTANG SUHU TERTENTU UNTUK APLIKA … more →

Tags: Software, Research, endf, Data Nuklir

Calculating time between two MCNP timestamps

Andrei wrote 2 years ago: Doing performance tests with MCNP-like code, I needed to calculate time between two time points form … more →

Tags: Programming, Ruby

Perhitungan Kritikalitas dengan MCNP

komputasibatan wrote 3 years ago: View this document on Scribd … more →

Tags: Fisika Reaktor Nuklir, Monte Carlo

Estimasi Fluks Neutron 4 comments

tsdipura wrote 4 years ago:             Secara umum, fluks neutron dapat ditentukan atau dihitung dengan dua cara yaitu metoda d … more →

Tags: Fisika Reaktor Nuklir, neutronic, neutron flux, Monte Carlo, track-length estimate


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