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Gamma electron coupled simulation
  • Salman Khan
  • · Replies 2 ·
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2
MCNPX memory error: "bad trouble in imcn in routine dynamic allocation"
  • Nagib Benamer
  • · Replies 1 ·
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1
How to Calculate the Source Activity from Dose Rate in MCBEND
  • gxa
  • · Replies 0 ·
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0
Energy Spectrum Attenuation
  • MadGander
  • · Replies 14 ·
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14
How does MNCP calculate an F6 Tally?
  • MadGander
  • · Replies 1 ·
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1
MCNP Modelling Detector Energy Response Vs Empirical Results
  • jjames_gunn
  • · Replies 3 ·
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3
Nuclear Power Gets a Big Boost in the US
  • gleem
  • · Replies 5 ·
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5
Analyzing Pulse Height vs. Time Response of a Scintillator Detector in Front of a Pulsed X-Ray Source
  • Salman Khan
  • · Replies 1 ·
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1
Why Are MCNP Photons Getting Lost?
  • MadGander
  • · Replies 13 ·
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13
radioactive iodine - risk of exposure
  • Thygal21
  • · Replies 2 ·
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2
Low energy Photon Simulation in MCNP
  • Salman Khan
  • · Replies 4 ·
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4
Approval from China’s State Council to add four AP1000 plants
  • gmax137
  • · Replies 3 ·
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3
NuScale, UAMPS terminate small modular reactor project in Idaho
  • gmax137
  • · Replies 16 ·
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16
Fatal error: "entries are not monotonically increasing"
  • Basmah
  • · Replies 1 ·
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1
Question about counting rate in a detector
  • Alexander Camargo
  • · Replies 1 ·
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1
Compton scattering in MCNP
  • Salman Khan
  • · Replies 2 ·
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2
Strange MCNP Fatal Error due to my material card?
  • MadGander
  • · Replies 6 ·
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6
Dose rate measurement through MCNP
  • Salman Khan
  • · Replies 4 ·
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4
Help, try to make one analysis in the RITM-200 reactor series, but can't find some informartion... any tips?
  • yukio
  • · Replies 4 ·
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4
MCNP: Help constructing the geometry for this pinpoint chamber please
  • Alexander Camargo
  • · Replies 8 ·
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8
Design error in reactor nuclear simulation in serpent code
  • emilmammadzada
  • · Replies 1 ·
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1
Why Are Burnup Numbers Identical for Different Fuels in MCNP?
  • Rafimah
  • · Replies 3 ·
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3
Help Needed with MCNP Simulation for Brachytherapy Treatment Room
  • GeneDeitch
  • · Replies 1 ·
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1
Why is My MCNP Burnup Calculation Failing?
  • Rafimah
  • · Replies 1 ·
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1
Computation for nuclear reactor systems
  • Astronuc
  • · Replies 1 ·
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1
How to Determine Fission Rate in MCNP6?
  • J Chancleto
  • · Replies 4 ·
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4
PIG (Penning Ionization Gauge) Ion source
  • sam2212
  • · Replies 20 ·
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20
Could Flattened End Magnets Improve Magnetic Mirror Traps?
  • FusionJim
  • · Replies 9 ·
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9
MCNPX Transformation
  • ifa23
  • · Replies 14 ·
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14
Endothermic and Threshold reactions - Are they Equivalent?
  • Michal Kovac
  • · Replies 3 ·
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3
Question regarding fusion reaction containment and procedure
  • Hayes
  • · Replies 3 ·
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3
I need help in solving the problem of the code written with MCNPX 2.6
  • mo256
  • · Replies 2 ·
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2
Vogtle 4 initial criticality
  • gmax137
  • · Replies 3 ·
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3
MCNP: Declaring two sources in two cells
  • lee phong
  • · Replies 6 ·
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6
Validating "NET Power's" use of the Allam-Fetvedt cycle
  • Joseph M. Zias
  • · Replies 6 ·
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6
MCNP6: Energy and angular distribution of neutrons after moderation
  • louisdpt04
  • · Replies 6 ·
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6
Plotting more than one tally together in VISED MCNP version
  • alaa y okasha
  • · Replies 1 ·
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1
Learning VisEd for MCNP
  • steph_ws23
  • · Replies 0 ·
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0
MCNP Summary Table: Explanation and Use
  • DEvens
  • · Replies 5 ·
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5
Fukushima Fukushima Daiichi nuclear disaster discussions
  • Borek
  • · Replies 12 ·
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12
Radioisotope Decay Simulation in MCNP6
  • frhnsaif
  • · Replies 5 ·
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5
To simulate the interaction of gamma photons with only oxygen (O) atom
  • Marina123456
  • · Replies 2 ·
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2
Are spent nuclear fuel rods radioactive?
  • lighthouse1234
  • · Replies 21 ·
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21
Can Any Country Achieve Net Zero Without Nuclear?
  • bhobba
  • · Replies 191 ·
7
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191
New Salt Cooled Nuclear Reactor Approved by NRC
  • gleem
  • · Replies 30 ·
2
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30
How can I fix the illegal data signal error in my FMESH tally code in MCNP6?
  • Marina123456
  • · Replies 1 ·
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1
Have pulsed fission reactors got any potential in nuclear energy?
  • DyerMaker
  • · Replies 5 ·
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5
MCNP6 gamma dose tally problems
  • skoch
  • · Replies 5 ·
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5
Reproducing (almost) Oklo reactor conditions in the lab
  • galvdoc
  • · Replies 6 ·
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6
Confirmation of Laser Fusion Break Even Point
  • jedishrfu
  • · Replies 0 ·
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0
MCNP: Can I input the X-Ray tube voltage in MCNP source specification?
  • Anisur Rahman
  • · Replies 8 ·
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8
Can Small Modular Reactors Revitalize Nuclear-Powered Surface Combatants?
  • Vanadium 50
  • · Replies 45 ·
2
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45
Is it possible to use TR or TRCL to translate an F4 or FMESH4 tally in MCNP6.2?
  • 19matthew89
  • · Replies 4 ·
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4
How is Alpha Particle Energy Defined in MCNP6?
  • physadict
  • · Replies 0 ·
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0
Solving Fatal Error in MCNP6 Particle Alpha Mode
  • physmcnp6
  • · Replies 7 ·
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7
Describing cosmic particles in mcnp6
  • zhj2024
  • · Replies 3 ·
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3
Does the hydrogen bomb emit beta radiation?
  • ahmeds
  • · Replies 6 ·
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6
What is the practical size of a neutron research reactor?
  • Josiah
  • · Replies 14 ·
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14
Atomic density of Oxygen in a composite
  • emilmammadzada
  • · Replies 6 ·
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6
What Is the Difference Between Angular Neutron Flux and Neutron Current Vector?
  • badvot
  • · Replies 2 ·
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2
Elevated Geiger Counter Radiation Reading for Envelope?
  • jun192022
  • · Replies 26 ·
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26
MCNP code for Neutron Spectroscopy
  • Hamidul
  • · Replies 17 ·
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17
Fukushima Candu Reactor compared k_eff values with Serpent
  • emilmammadzada
  • · Replies 0 ·
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0
Why can't we simply use an atomic bomb to get the fusion working?
  • Rfael
  • · Replies 18 ·
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18
Need help ordering parts for a nuclear fusion reactor
  • Mathiasrd
  • · Replies 5 ·
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5
Calculating Microdosimetry in MCNP
  • Mingzhu
  • · Replies 15 ·
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15
How to Declare a Spherical Neutron Source for Thermal Neutron Flux Calculation?
  • Addali sabah
  • · Replies 2 ·
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2
Sources for nuclear fuel pellet fabrication methods?
  • Phys pilot
  • · Replies 7 ·
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7
Error running example ICRP145_HumanPhantoms in Geant4
  • emilmammadzada
  • · Replies 0 ·
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0
Westinghouse Very Small Modular Reactor Progress
  • gmax137
  • · Replies 6 ·
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6
Help with neutron spectroscopy experiments in MCNP code
  • Hamidul
  • · Replies 19 ·
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19
Radioistope Power Systems (RPS) and Pu-238
  • Astronuc
  • · Replies 0 ·
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0
MCNP Problem - Bad character in column 2
  • KOKI
  • · Replies 7 ·
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7
Best software to simulate the radiation emitted by uranium powder inside a pipe?
  • Phys pilot
  • · Replies 4 ·
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4
Double differential cross section in Fluka
  • emilmammadzada
  • · Replies 0 ·
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0
How Can I Simulate a Narrow Spectrum X-Ray Beam Using MCNP?
  • Anisur Rahman
  • · Replies 9 ·
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9
Problem with Moritz (3D viewer of MCNPX)
  • ThibautVincho
  • · Replies 4 ·
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4
FLUKA: Why Does Neutron Flux Increase When Passing Through a Moderator?
  • mudmucker
  • · Replies 5 ·
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5
How to Convert TMESH Data to Text Files in MCNP6 Using Python"
  • rai915
  • · Replies 4 ·
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4
Background Analysis for MCBEND Simulation
  • gxa
  • · Replies 0 ·
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0
Question about Source Probability in MCNP
  • Anisur Rahman
  • · Replies 1 ·
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1
MCNPX Fatal error: "electron importances are zero"
  • Elizabeth Vega
  • · Replies 3 ·
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3
What is the physical significance of WGT and SBn in MCNP source specifications?
  • Anisur Rahman
  • · Replies 1 ·
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1
MCNP -- What is meant by 2M and 20R?
  • Anisur Rahman
  • · Replies 2 ·
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2
How to check the isotropy of the source in MCNP?
  • angfells
  • · Replies 2 ·
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2
Need Recommendations for Nuclear Reaction Modelling Software
  • Todobek
  • · Replies 2 ·
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2
Particles produced and energies in the target Geant4
  • emilmammadzada
  • · Replies 7 ·
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7
Positioning of Capacitance in Ionization Chamber's Equivalent Circuit
  • Simobartz
  • · Replies 4 ·
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4
Gaussian Energy Broadening tally
  • gxa
  • · Replies 1 ·
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1
How far do fission products travel?
  • mesa
  • · Replies 10 ·
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10
MCNP6: error -- "bad trouble in imcn" is usually tangled with spacing error?
  • HHJo
  • · Replies 6 ·
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6
Understanding MCNP Tally F5 Output: Tips for Beginners
  • Sonong
  • · Replies 1 ·
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1
What actually happens to the U-238 part of fuel in a nuclear reactor?
  • oblong-pea
  • · Replies 7 ·
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7
Real Experiment-MCBEND Simulation
  • gxa
  • · Replies 6 ·
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6
Experiment-Simulation comparing count values in MCNP
  • gkcn
  • · Replies 17 ·
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17
Meaning of "Average" Flux Tallies in MCNP
  • a1234
  • · Replies 1 ·
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1
Isotropic distribution for a surface source MCNP
  • angfells
  • · Replies 4 ·
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4
Chernobyl Chernobyl tourism visit caused contamination?
  • eas1234
  • · Replies 4 ·
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4
Dose calculation for oscilloscope
  • Salman Khan
  • · Replies 7 ·
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7
Gamma Ray Shielding -- How much is enough?
  • Salman Khan
  • · Replies 5 ·
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5