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Collecting MCU (Monte Carlo Universal) Input files
- DAntanov
- · Replies 3 ·
Are catalyzed fusion reactors (LENR) credible or another cold fusion claim?
- Flyboy
- · Replies 3 ·
Gamma electron coupled simulation
- Salman Khan
- · Replies 2 ·
MCNPX memory error: "bad trouble in imcn in routine dynamic allocation"
- Nagib Benamer
- · Replies 1 ·
How to Calculate the Source Activity from Dose Rate in MCBEND
- gxa
- · Replies 0 ·
Energy Spectrum Attenuation
- MadGander
- · Replies 14 ·
How does MNCP calculate an F6 Tally?
- MadGander
- · Replies 1 ·
MCNP Modelling Detector Energy Response Vs Empirical Results
- jjames_gunn
- · Replies 3 ·
Nuclear Power Gets a Big Boost in the US
- gleem
- · Replies 5 ·
Pulse height vs. time response with MCNP F8 tally for pulsed X-ray scintillator
- Salman Khan
- · Replies 1 ·
Why Are MCNP Photons Getting Lost?
- MadGander
- · Replies 13 ·
radioactive iodine - risk of exposure
- Thygal21
- · Replies 2 ·
Low energy Photon Simulation in MCNP
- Salman Khan
- · Replies 4 ·
Approval from China’s State Council to add four AP1000 plants
- gmax137
- · Replies 3 ·
NuScale, UAMPS terminate small modular reactor project in Idaho
- gmax137
- · Replies 16 ·
Fatal error: "entries are not monotonically increasing"
- Basmah
- · Replies 1 ·
Using MCNP tally time bins to calculate detector counting rate
- Alexander Camargo
- · Replies 1 ·
Compton scattering in MCNP
- Salman Khan
- · Replies 2 ·
Strange MCNP Fatal Error due to my material card?
- MadGander
- · Replies 6 ·
Dose rate measurement through MCNP
- Salman Khan
- · Replies 4 ·
MCNP geometry definition for a pinpoint ionization chamber
- Alexander Camargo
- · Replies 8 ·
Design error in reactor nuclear simulation in serpent code
- emilmammadzada
- · Replies 1 ·
Why Are Burnup Numbers Identical for Different Fuels in MCNP?
- Rafimah
- · Replies 3 ·
MCNP geometry errors in brachytherapy room with concrete walls
- GeneDeitch
- · Replies 1 ·
Why is My MCNP Burnup Calculation Failing?
- Rafimah
- · Replies 1 ·
Computation for nuclear reactor systems
- Astronuc
- · Replies 1 ·
How to Determine Fission Rate in MCNP6?
- J Chancleto
- · Replies 4 ·
PIG (Penning Ionization Gauge) Ion source
- sam2212
- · Replies 20 ·
Could Flattened End Magnets Improve Magnetic Mirror Traps?
- FusionJim
- · Replies 9 ·
MCNPX Transformation
- ifa23
- · Replies 14 ·
Endothermic and Threshold reactions - Are they Equivalent?
- Michal Kovac
- · Replies 3 ·
Question regarding fusion reaction containment and procedure
- Hayes
- · Replies 3 ·
Gamma results from MCNPX 2.6 simulation at 719 keV
- mo256
- · Replies 2 ·
Vogtle 4 initial criticality
- gmax137
- · Replies 3 ·
MCNP: Declaring two sources in two cells
- lee phong
- · Replies 6 ·
Validating "NET Power's" use of the Allam-Fetvedt cycle
- Joseph M. Zias
- · Replies 6 ·
MCNP6: Energy and angular distribution of neutrons after moderation
- louisdpt04
- · Replies 6 ·
Plotting more than one tally together in VISED MCNP version
- alaa y okasha
- · Replies 1 ·
Learning VisEd for MCNP
- steph_ws23
- · Replies 0 ·
MCNP Summary Table: Explanation and Use
- DEvens
- · Replies 5 ·
Fukushima Fukushima Daiichi nuclear disaster discussions
- Borek
- · Replies 12 ·
Radioisotope Decay Simulation in MCNP6
- frhnsaif
- · Replies 5 ·
To simulate the interaction of gamma photons with only oxygen (O) atom
- Marina123456
- · Replies 2 ·
Are spent nuclear fuel rods radioactive?
- lighthouse1234
- · Replies 21 ·
Can Any Country Achieve Net Zero Without Nuclear?
- bhobba
- · Replies 191 ·
New Salt Cooled Nuclear Reactor Approved by NRC
- gleem
- · Replies 30 ·
How can I fix the illegal data signal error in my FMESH tally code in MCNP6?
- Marina123456
- · Replies 1 ·
Have pulsed fission reactors got any potential in nuclear energy?
- DyerMaker
- · Replies 5 ·
MCNP6 gamma dose tally problems
- skoch
- · Replies 5 ·
Reproducing (almost) Oklo reactor conditions in the lab
- galvdoc
- · Replies 6 ·
Confirmation of Laser Fusion Break Even Point
- jedishrfu
- · Replies 0 ·
MCNP: Can I input the X-Ray tube voltage in MCNP source specification?
- Anisur Rahman
- · Replies 8 ·
Can Small Modular Reactors Revitalize Nuclear-Powered Surface Combatants?
- Vanadium 50
- · Replies 45 ·
Is it possible to use TR or TRCL to translate an F4 or FMESH4 tally in MCNP6.2?
- 19matthew89
- · Replies 4 ·
How is Alpha Particle Energy Defined in MCNP6?
- physadict
- · Replies 0 ·
Solving Fatal Error in MCNP6 Particle Alpha Mode
- physmcnp6
- · Replies 7 ·
Describing cosmic particles in mcnp6
- zhj2024
- · Replies 3 ·
Does the hydrogen bomb emit beta radiation?
- ahmeds
- · Replies 6 ·
What is the practical size of a neutron research reactor?
- Josiah
- · Replies 14 ·
Atomic density of Oxygen in a composite
- emilmammadzada
- · Replies 6 ·
What Is the Difference Between Angular Neutron Flux and Neutron Current Vector?
- badvot
- · Replies 2 ·
Elevated Geiger Counter Radiation Reading for Envelope?
- jun192022
- · Replies 26 ·
MCNP code for Neutron Spectroscopy
- Hamidul
- · Replies 17 ·
Fukushima Candu Reactor compared k_eff values with Serpent
- emilmammadzada
- · Replies 0 ·
Why can't we simply use an atomic bomb to get the fusion working?
- Rfael
- · Replies 18 ·
Sourcing a spherical metal vacuum chamber with international shipping
- Mathiasrd
- · Replies 5 ·
Calculating Microdosimetry in MCNP
- Mingzhu
- · Replies 15 ·
How to Declare a Spherical Neutron Source for Thermal Neutron Flux Calculation?
- Addali sabah
- · Replies 2 ·
Sources for nuclear fuel pellet fabrication methods?
- Phys pilot
- · Replies 7 ·
Error running example ICRP145_HumanPhantoms in Geant4
- emilmammadzada
- · Replies 0 ·
Westinghouse Very Small Modular Reactor Progress
- gmax137
- · Replies 6 ·
MCNP data cards for neutron spectroscopy geometry
- Hamidul
- · Replies 19 ·
Radioistope Power Systems (RPS) and Pu-238
- Astronuc
- · Replies 0 ·
MCNP Problem - Bad character in column 2
- KOKI
- · Replies 7 ·
Best software to simulate the radiation emitted by uranium powder inside a pipe?
- Phys pilot
- · Replies 4 ·
Double differential cross section in Fluka
- emilmammadzada
- · Replies 0 ·
How Can I Simulate a Narrow Spectrum X-Ray Beam Using MCNP?
- Anisur Rahman
- · Replies 9 ·
Problem with Moritz (3D viewer of MCNPX)
- ThibautVincho
- · Replies 4 ·
FLUKA: Why Does Neutron Flux Increase When Passing Through a Moderator?
- mudmucker
- · Replies 5 ·
How to Convert TMESH Data to Text Files in MCNP6 Using Python"
- rai915
- · Replies 4 ·
Background Analysis for MCBEND Simulation
- gxa
- · Replies 0 ·
What does source probability represent in MCNP when values exceed 1?
- Anisur Rahman
- · Replies 1 ·
MCNPX Fatal error: "electron importances are zero"
- Elizabeth Vega
- · Replies 3 ·
What is the physical significance of WGT and SBn in MCNP source specifications?
- Anisur Rahman
- · Replies 1 ·
MCNP -- What is meant by 2M and 20R?
- Anisur Rahman
- · Replies 2 ·
How to check the isotropy of the source in MCNP?
- angfells
- · Replies 2 ·
Need Recommendations for Nuclear Reaction Modelling Software
- Todobek
- · Replies 2 ·
Particles produced and energies in the target Geant4
- emilmammadzada
- · Replies 7 ·
Positioning of Capacitance in Ionization Chamber's Equivalent Circuit
- Simobartz
- · Replies 4 ·
Gaussian Energy Broadening tally
- gxa
- · Replies 1 ·
How far do fission products travel?
- mesa
- · Replies 10 ·
MCNP6: error -- "bad trouble in imcn" is usually tangled with spacing error?
- HHJo
- · Replies 6 ·
How to read MCNP Tally F5 output for collided and uncollided photon flux
- Sonong
- · Replies 1 ·
What actually happens to the U-238 part of fuel in a nuclear reactor?
- oblong-pea
- · Replies 7 ·
Real Experiment-MCBEND Simulation
- gxa
- · Replies 6 ·
NaI(Tl) measurement and MCNP simulation count discrepancy
- gkcn
- · Replies 17 ·
Meaning of "Average" Flux Tallies in MCNP
- a1234
- · Replies 1 ·
Isotropic distribution for a surface source MCNP
- angfells
- · Replies 4 ·
Chernobyl Chernobyl tourism visit caused contamination?
- eas1234
- · Replies 4 ·