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Why is My MCNP Program Outputting Too Small a Value?
  • angfells
  • · Replies 2 ·
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Best Dosimeter for 10 ns Pulse Dose Measurement
  • Salman Khan
  • · Replies 9 ·
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Reactor refrigeration without external power supply
  • Gruxg
  • · Replies 5 ·
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Is there anyone here who uses the Mesh tally in MCNPX?
  • QEROURI ASSIYA
  • · Replies 1 ·
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Creating FMESH Tally Over Region - Troubleshooting
  • nrat320
  • · Replies 1 ·
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1
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Thermal neutron detection using MCNP
  • Islam Nabil
  • · Replies 3 ·
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3
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Product Cross Section For Zn66 in Geant4
  • emilmammadzada
  • · Replies 1 ·
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1
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Dose recording on Pocket dosimeter -- Is it accurate for a person's whole body?
  • Salman Khan
  • · Replies 7 ·
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7
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Why am I seeing a discrepancy in photon energy when doping ZnS:Ag in MCNP 6.1?
  • nrat320
  • · Replies 6 ·
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6
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Codes to calculate diffusion parameters of homogeneous reactor
  • DeltaMed910
  • · Replies 3 ·
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3
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MCNP6.2 - SSW and surfaces defining universe boundaries
  • 19matthew89
  • · Replies 1 ·
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1
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Plot Mesh Tally with MCNP - Help request from Carla
  • carlepy
  • · Replies 3 ·
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3
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MCNP6.2 - Combination of transformations
  • 19matthew89
  • · Replies 1 ·
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1
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Efficient MCNP Lattice Source Help: Defining Universes and Tallies in Cell File
  • ethnscot
  • · Replies 2 ·
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2
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MCNP: How to display particles outside the source?
  • Salman Khan
  • · Replies 1 ·
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MCNP Tally f8 unreliable since neutron transport is nonanalog
  • dando
  • · Replies 3 ·
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3
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Is quartarad radex 1503+ or GQ GMC-300E a good geiger counter?
  • Alberto Spain
  • · Replies 1 ·
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1
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MCNP: Ctme Card Impacts on Results
  • Salman Khan
  • · Replies 1 ·
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1
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Run MCNP 5 input file of certain geometry for flux calculation
  • Salman Khan
  • · Replies 8 ·
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8
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How to use mdata file data output by mesh card in mcnp software?
  • chengmo
  • · Replies 1 ·
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1
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What is a unit of time listed in MCNP6 PTRAC output file?
  • jj8bmk
  • · Replies 1 ·
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1
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MCNP: Measure Dosage in Concrete with tmesh Cards
  • chengmo
  • · Replies 1 ·
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1
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MCNP6.2 - ENDF/B reaction numbers for tally multiplier
  • 19matthew89
  • · Replies 10 ·
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10
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I use tmesh card to get mdata file, what tool should I use to draw？
  • chengmo
  • · Replies 1 ·
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1
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2K
Basic FMESH question: "Jmesh keyword missing error"
  • AlexFi
  • · Replies 4 ·
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4
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Fluka user routines -- Questions about Input and Output files
  • emilmammadzada
  • · Replies 1 ·
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1
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MCNP6 BURN -- Testing about burnable poison depletion
  • goyu96
  • · Replies 1 ·
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1
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MCNP terminology question -- Effective Full Power Days (EFPDs)
  • Rofida
  • · Replies 1 ·
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1
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SSW of a translated cell (via TRCL)?
  • 19matthew89
  • · Replies 1 ·
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1
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How Does MCNP Macro Definition Modeling Work?
  • chengmo
  • · Replies 1 ·
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1
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Can MCNP solve the geometric coincidence issue with a semi-cylinder and cuboid?
  • chengmo
  • · Replies 6 ·
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6
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2K
Why is my SSW/SSR code not producing readable output from a KCODE run?
  • 19matthew89
  • · Replies 3 ·
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3
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Help debugging MCNP code - particle lost and zero latice element found
  • AlexFi
  • · Replies 3 ·
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3
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Why Do MCNP5 Statistical Tests Fail Despite Increasing Particle Numbers?
  • Van525
  • · Replies 6 ·
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6
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Is There an Issue with My MCNP Macro Definition Modeling?
  • chengmo
  • · Replies 1 ·
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1
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I have a problem on my MCNP5 cross-section library
  • Islam Nabil
  • · Replies 1 ·
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1
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Absorbed dose: organ dose manual calculation
  • emilmammadzada
  • · Replies 1 ·
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1
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MCNP6.2 - SDEF on a RCC surface
  • 19matthew89
  • · Replies 1 ·
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1
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Need a 3d scatter plot with connected lines
  • Islam Nabil
  • · Replies 1 ·
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1
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14MeV neutrons in MCNP interact with carbon without producing alpha
  • jianggong
  • · Replies 5 ·
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5
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Radionuclides used in nuclear medicine
  • emilmammadzada
  • · Replies 3 ·
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3
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I need an MCNP simulated APR1400 input file
  • Islam Nabil
  • · Replies 10 ·
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10
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How can I find the stopping power for a single energy value in FLUKA?
  • emilmammadzada
  • · Replies 1 ·
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1
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MCNP FMESH for Plotting power distribution
  • AlexFi
  • · Replies 15 ·
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15
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MCNP6.2 - Source particle started in a cell of zero importance
  • 19matthew89
  • · Replies 7 ·
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7
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Jules Horowitz Reactor (JHR) Material Test Reactor
  • Astronuc
  • · Replies 0 ·
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0
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What is the current status of Vogtle Unit 3?
  • gmax137
  • · Replies 1 ·
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1
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MCNP6.2 - SDEF position related keywords
  • 19matthew89
  • · Replies 3 ·
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3
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MCNP lattice of the fuel assembly input file?
  • Islam Nabil
  • · Replies 10 ·
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10
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Calculation of activation with mesh tally in MCNPX 2.6
  • Gogy
  • · Replies 5 ·
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5
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I get this error when I try to run the code MCNPX
  • emilmammadzada
  • · Replies 5 ·
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5
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MCNP Surface Tallies: F1 & F2 on Infinite Cylinders & Planes
  • 19matthew89
  • · Replies 5 ·
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5
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MCNP6.2 - Are results of FMESH tallies already divided by cell volume?
  • 19matthew89
  • · Replies 2 ·
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2
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Hysplit.v5.2.3_UbuntuOS20.04.4LTS_public compiling erorr
  • emilmammadzada
  • · Replies 7 ·
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7
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MCNP6.2: F6:N and F6:P tallies vs +F6 tallies?
  • 19matthew89
  • · Replies 3 ·
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3
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Optimizing Filter Thickness in MCNP5 for Phosphorus 32 Bremsstrahlung Reduction
  • Addali sabah
  • · Replies 6 ·
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6
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Does Jimmy Carter's long life prove some exposure to radiation is OK?
  • swampwiz
  • · Replies 1 ·
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1
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Why Does MCNP Delete Surfaces in Hexagonal Fuel Element Simulations?
  • AlexFi
  • · Replies 5 ·
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5
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If MCNP tallies are normalized, shouldn't they be <1?
  • 19matthew89
  • · Replies 5 ·
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5
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4K
MCNP - z-coordinates of cylindrical mesh >0?
  • 19matthew89
  • · Replies 2 ·
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2
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FRENDY nuclear code -- Where to download it? (for ubuntu 22.04)
  • emilmammadzada
  • · Replies 6 ·
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6
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What is the difference between FMESH and MESH in MCNP?
  • 19matthew89
  • · Replies 1 ·
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1
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MCNP - Tallies definition with "<"
  • 19matthew89
  • · Replies 2 ·
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2
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Simulate3: Modeling 3-Batch Equilibrium Cycle for PWR
  • tonidous
  • · Replies 4 ·
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4
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Major Nuclear Fusion Milestone: Ignition Achieved
  • phyzguy
  • · Replies 34 ·
2
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34
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Optimize Filter Thickness with MCNP5 for Phosphorus 32 Bremsstrahlung
  • Addali sabah
  • · Replies 6 ·
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6
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Skyshine vs Direct Dose in MCNP5
  • Will_007
  • · Replies 4 ·
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4
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FRENSIE installing and compiling error
  • emilmammadzada
  • · Replies 6 ·
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6
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Running the tests njoy16 in ubuntu terminal
  • emilmammadzada
  • · Replies 15 ·
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15
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NuScale Modular Reactor gets NRC certification
  • gleem
  • · Replies 1 ·
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1
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Stopping power and projected range for FLUKA code
  • emilmammadzada
  • · Replies 1 ·
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1
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Where Are the Other Detectors for F5 Tally in MCNP?
  • Will_007
  • · Replies 4 ·
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4
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Modeling and Simulation in Nuclear Energy
  • Astronuc
  • · Replies 1 ·
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1
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Troubleshooting MCNP k_eff for Space Reactor Core: Tips and Tricks"
  • AlexFi
  • · Replies 11 ·
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11
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Why Don't GM Counters Detect Alpha Particles?
  • Vilius
  • · Replies 7 ·
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7
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How to Fix OpenMc Installing Error in Terminal?
  • emilmammadzada
  • · Replies 2 ·
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2
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Big announcement about fusion energy coming soon (Dec-2022)
  • swampwiz
  • · Replies 129 ·
5
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129
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12K
Did Installing ENDFVII Fix the MCNP5 Error in Routine IMCN?
  • Limitzone
  • · Replies 6 ·
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6
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Searching for a single and complete resource about nuclear fuels
  • mark_bose
  • · Replies 8 ·
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8
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PTRAC File - MCNP - Multi-core computing
  • Luizpo
  • · Replies 1 ·
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1
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How do I install FLUKA on Windows 10 using WSL and Ubuntu 20.04?
  • emilmammadzada
  • · Replies 3 ·
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3
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Particle transporting (FLIBE) -Geant4
  • emilmammadzada
  • · Replies 1 ·
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1
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Fixing MCNPX Fatal Error: Too Many Numbers First Entry
  • emilmammadzada
  • · Replies 19 ·
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19
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MCNP6.2 BURN Problem Uranium Dioxide 4.2% Enrichment
  • mhovi
  • · Replies 4 ·
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4
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Hybrid/variable spectrum reactor
  • armoredchestnut
  • · Replies 4 ·
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4
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Why do I always get 0 values in the radiation part? (MCNP5)
  • emilmammadzada
  • · Replies 58 ·
2
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58
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Particles transporting in MCNP5
  • emilmammadzada
  • · Replies 11 ·
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11
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Cylindrical and Symmetrical Nuclear Fusion Reactor
  • MartinG
  • · Replies 19 ·
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19
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How to Simulate Charged-Particle Energy-Loss Straggling in MCNP5?
  • emilmammadzada
  • · Replies 6 ·
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6
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Nuclear fusion and anti-nuclear technology
  • thewowsignal
  • · Replies 8 ·
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8
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Fusion catalized from graphite?
  • CCatalyst
  • · Replies 16 ·
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16
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Error: no plot because it would be empty, using mcnpx
  • hu94mcnpx
  • · Replies 3 ·
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3
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Fusion tritium problem solution?
  • artis
  • · Replies 9 ·
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9
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MCNP6 with mpi failed with signal 11 (Segmentation fault)
  • Albert ZHANG
  • · Replies 3 ·
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3
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[MCNP] Lost too much Keff with Burnup card
  • lee6853
  • · Replies 5 ·
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5
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Would wearing sunscreen help during a nuclear disaster/attack?
  • MELJA
  • · Replies 16 ·
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16
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Small yield of tactical nuclear weapons
  • Thecla
  • · Replies 2 ·
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2
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Does radon remain inside solid radium?
  • Philip Koeck
  • · Replies 9 ·
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9
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Nuclear Energy reading material
  • DTMsurf
  • · Replies 9 ·
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9
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New approach to stabilize fusion plasmas
  • Tom.G
  • · Replies 4 ·
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4
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