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