Join other experts in discussion on nuclear engineering. Topics on design and construction and operation of nuclear reactors. Radiation Protections, Radioactive Waste, Design, Reactors as well!
Threads
- Sticky
Understanding Radiation and Radiological Health: A Comprehensive Guide
- Astronuc
- · Replies 9 ·
Fukushima Japan Earthquake: nuclear plants Fukushima part 2
- Greg Bernhardt
- · Replies 2K ·
Can I use MCNP on ARM devices?
- Nikel
- · Replies 4 ·
Simulating an RBMK-1500 like the one in Ignalina
- KriegerTomate
- · Replies 3 ·
How close are we to getting micro reactors?
- Josiah
- · Replies 7 ·
Calculating Electron Yield by Photon Saturation in MCNP
- Salman Khan
- · Replies 2 ·
Regarding Weight Window Generation Iteration in MCNP
- LeoKong
- · Replies 3 ·
What Geiger Counter is best for this?
- DEvens
- · Replies 7 ·
How to draw a complex geometry in MCNP?
- Salman Khan
- · Replies 1 ·
MCNP PTRAC card help
- MadGander
- · Replies 1 ·
Geiger Counter Question
- worriedsick79
- · Replies 22 ·
Configuration of JEFF-3.3 Nuclear Data Library in MCNP6
- HEU_LL
- · Replies 3 ·
Particles lost in MCNP running
- flashcflash
- · Replies 5 ·
How effective is nuclear propulsion?
- Josiah
- · Replies 14 ·
Penning ion source test
- sam2212
- · Replies 2 ·
How to apply Nemtab cross section library into PARCS?
- annakaka
- · Replies 1 ·
Another SMR on the Horizon
- gleem
- · Replies 3 ·
Normalization of MCNP F4:P photon flux tally to experimental counts
- Marinaromany
- · Replies 5 ·
Nuclear Engineering and Propulsion Journals
- jirehnuclear2025
- · Replies 4 ·
Geometry modeling of an X-ray Irradiator
- Hamidul
- · Replies 5 ·
MCNP IMP:n=0 when IMP:p,e=1
- Adina C
- · Replies 2 ·
MCNP vs Serpent pin-cell burnup discrepancy in keff evolution
- emilmammadzada
- · Replies 5 ·
MCNP always saying my codes missed a cell
- flashcflash
- · Replies 4 ·
What type of energy is actually stored inside an atom?
- davLev
- · Replies 18 ·
Creating the geometry using MNCPX VisEd
- ugata88
- · Replies 4 ·
MCNP Code Error -- Need to find the cause of the error
- Anisur Rahman
- · Replies 7 ·
Separate the inelastic and capture reactions in a tally
- Alexander Camargo
- · Replies 6 ·
MCNP6 BURN Card Issue: Zero Burnup for Material in Fuel Assembly
- HEU_LL
- · Replies 2 ·
Interesting Documentary on the Dounreay Breeder Reactor
- gmax137
- · Replies 5 ·
Beginner Seeking Help: MCNP6 Burnup Example (OECD-NEA Benchmark)
- HEU_LL
- · Replies 6 ·
Fusion research idea involving more pressure
- Xebiqe
- · Replies 3 ·
eVinci MCNP input file
- igomaa51
- · Replies 3 ·
What Could Be Causing Unexpected Results in the LET Analysis with MCNP6.2?
- lucasfaraujo
- · Replies 8 ·
Help Needed: Discrepancy in 2D Monte Carlo Neutron Transport Simulation
- emilmammadzada
- · Replies 1 ·
Is nuclear fusion without radioactive waste possible?
- Chiel555
- · Replies 1 ·
Mesh Tally in MCNPX for Dose Calculation / How to Add & Visualize?
- Ayb_mcnp
- · Replies 0 ·
Shielded and unshielded dose from a Co-60 source are the same?
- Joao Pedro
- · Replies 2 ·
MCNP: Is this a valid way to define "two sources with different sizes"?
- BaoNgoc
- · Replies 1 ·
Atomic displacements, replacements, and radiation damage of structural materials
- Astronuc
- · Replies 1 ·
MCNPX output proton energy is zero?
- ameermukhtar
- · Replies 8 ·
MCNP6.2 - How to plot normalized tallies with MCNP6.2?
- 19matthew89
- · Replies 3 ·
Geometry error in newcel
- Jaddyd
- · Replies 8 ·
How to deal with Strong Anisotropic Scattering in multigroup Monte Carlo
- zjlei
- · Replies 0 ·
Help to run input file (MCNPX)
- zakaria
- · Replies 4 ·
Simulation of Pu-238 Decay
- omarkhairallah
- · Replies 2 ·
Anode in center of a magnetic confinement fusion device?
- MartinFick
- · Replies 2 ·
MCNP PTRAC filters
- MadGander
- · Replies 1 ·
China plans world’s first fusion-fission power plant
- kodama
- · Replies 23 ·
Reflector flux contribution
- ameermukhtar
- · Replies 4 ·
The MCNP code never ends, what went wrong?
- momomo
- · Replies 5 ·
Need help with this MCNPX Error
- unique empire
- · Replies 1 ·
How to convert MCNP-generated data
- Hamidul
- · Replies 4 ·
I need help please for Simulation of Xenon Oscillations in a Nuclear Reactor
- TOULA
- · Replies 4 ·
MCNP Geometry Error
- MadGander
- · Replies 1 ·
MCNP6 Reproduction of 40 MeV D - Li Target Experiment
- zhaozq
- · Replies 1 ·
I want to see the peak for an explosive detector simulation in MCNP
- kg09889
- · Replies 1 ·
How to use this MCNP physics model?
- kg09889
- · Replies 7 ·
Error: "MCNP bank is full. Bank backup file is being created."
- kg09889
- · Replies 0 ·
MCNP Deck Error: cannot create srctp
- MadGander
- · Replies 1 ·
12 yr old Makes a Nuclear Fusion Reactor
- jedishrfu
- · Replies 5 ·
MCNP: Integral flux crossing the spherical surface of a spherical cap
- xisco
- · Replies 4 ·
MCNP cone source definition
- MadGander
- · Replies 1 ·
Zero lattice element hit in MCNP6 (but I cannot find the wrong area)
- yqh
- · Replies 2 ·
Constellation Energy buying Calpine
- gmax137
- · Replies 1 ·
MCNP Data Card Errors
- MadGander
- · Replies 1 ·
Chernobyl New Safe Confinement structure struck by drone… what now?
- Flyboy
- · Replies 1 ·
Technical Discussion on TMESH Tally in MCNP 6.2 and 6.3
- alinegranja
- · Replies 2 ·
MCNP geometry error
- MadGander
- · Replies 1 ·
Best Point Gamma Source in MCNP simulation?
- Salman Khan
- · Replies 5 ·
How to Calculate Total Thermal Power in Nuclear Reactors?
- emilmammadzada
- · Replies 6 ·
Subroutine Sources option in MCNP
- thanhpham
- · Replies 4 ·
Addition of Central Control Rod in Small Modular Reactor Geometry Using Serpent
- emilmammadzada
- · Replies 0 ·
How is Uranium refined so it can be used in nuclear reactors?
- mathisrad
- · Replies 7 ·
How to Calculate Atomic Density for Borated Water (750 ppm) at 300 K?
- emilmammadzada
- · Replies 16 ·
Problem with photonuclear physics phys:p in MCNP
- Nour_wahban
- · Replies 2 ·
Questions about beta radiation shielding
- jun192022
- · Replies 6 ·
MCNP Barrel Geometry Help
- wtobias
- · Replies 4 ·
Literature on VVER-1200
- Anastasy
- · Replies 3 ·
Cooling systems in thermal power stations
- Gruxg
- · Replies 4 ·
Fukushima Fukushima -- possible alternate scenario?
- FusionJim
- · Replies 2 ·
Help with error in MCNP6: "Geometry error: no intersection found"
- ameermukhtar
- · Replies 7 ·
MCNP6 Error: "Geometry error: no cell found"
- ameermukhtar
- · Replies 3 ·
MCNP RHP/HEX Geometry Clarifications
- MadGander
- · Replies 1 ·
"10 particles lost" warning in MCNPX
- Nour_wahban
- · Replies 6 ·
Help with F4 Fm4 dose calculation in MCNP simulation
- alinegranja
- · Replies 7 ·
MCNPX ver 2.7 error: ''bad problem in xact in routine tpefil chg_mem error''
- alperbugraarslan
- · Replies 3 ·
How do I create an SDEF card for lattice geometry?
- Alexander Camargo
- · Replies 3 ·
How to Calculate Atom/B-cm Values for Nuclear Fuel Composition?
- emilmammadzada
- · Replies 6 ·
How to fix this error in MCNPX 2.7?
- ahb
- · Replies 1 ·
LCS error: bert.3 bert.2 when running BURN card MCNP
- Syifa S
- · Replies 4 ·
MCNP TR Transform Card Question
- MadGander
- · Replies 2 ·
Help debugging a geometry-related error in my MCNP input deck
- MadGander
- · Replies 5 ·
MCNPX pwr pin depletion input file running error
- emilmammadzada
- · Replies 15 ·
MCNP6: Cell Volume Not Calculated - Assymetrical
- NeutronWrangler
- · Replies 2 ·
Sabine on Small Nuclear Reactors
- BWV
- · Replies 3 ·
Question about multiple runtimes on MPI for MCNP6
- Alexander Camargo
- · Replies 5 ·
Collecting MCU (Monte Carlo Universal) Input files
- DAntanov
- · Replies 3 ·
Catalyzed fusion… hype, or reality?
- Flyboy
- · Replies 3 ·