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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!
Can reducing Boric acid concentrations extend the life of fuel assemblies?
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MCNP4 help: f4 tally in lattice
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Proton-Boron fusion feasibility
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MCNP5 tallies conversion and MCNPX
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Idiot with a Vision: Using a Diverter to Purify Plasma
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How does D-T fusion reaction utilize its waste to create more fuel?
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Binding energy and nuclear fission
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Determining Thorium requirements for conversion reactor
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Inertial confinement fusion (First light, NIF, etc)
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The length of the line in the MCNP cell card MCNP
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Why Might Beryllium Be Considered for Use in Nuclear Reactor Fuel?
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Typical PWR fuel assembly dimensions
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Any tips for debugging MCNP geometry errors?
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MCNP error : "geometry error in newcel"
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What is the best fast reactor fuel and why?
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How to Simulate Parallel Beams in MCNP5 or MCNPX?
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Chernobyl loses power, spent fuel storage question #Ukraine
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MCNP6: Getting a "10 particles got lost" error
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When do fission products get cooler than fuel?
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How to explain the effect of temperature profile on feedback coefficient?
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Is there a program that can run depletion calculations in reverse?
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How can I model both photons and neutrons with MCNP?
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Looking for a digital copy of the Table of Radioactive Isotopes
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Why don't we use Direct-Charging Radioisotope Generators?
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Ukraine nuclear power plant Zaporizhzhia on fire
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How much risk with first nuclear explosion test?
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NRC Reversing License Extensions
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An extremely basic question on MCNP
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Size Limitation of fuel Bundle in a nuclear reactor
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Fission Products that come from the MCNP output?
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Model UO2(5%)+Th+U233 Fuel in MCNPX for SCWR
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Constructing an Isotropic Point Source with Rectangular Beam in MCNPX
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Lithium hydroxide from Li-7 as used in thermal reactors
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Troubleshooting MCNP6.2 Error: l_list Too Small
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Uranium density in fuel meat/kernel
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I want to write my own Monte Carlo code for Neutron transport
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Clean lithium fission saltwater rocket
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How to deal with MCNP stack overflow
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Looking for specs on Failed Fuel Detectors on NPPs in US
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Can DRAGON/DONJON Code Handle Complex Boron Compositions in PWR Analysis?
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Mössbauer Effect: Remembering an Advanced Lab Experiment
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Coolant Mass Flow Rate Through Subchannel in Nuclear Fuel Assembly
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Neutron scattering probability distribution
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MCNP Output Data: Tutorials & PDFs for SCWR Criticality Analysis
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MCNP: Critical Mass of UO2 (10% Enrichment)
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Measurements with the CsI(Tl) detector
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Finding Peak Values & Calculating Efficiency from Energy & Count Data
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What is Baryon Decuplet in Physics?
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Supercritical Water Reactor: Density & Temperature Impact
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Can Spent Nuclear Fuel Be Used as an Alternate Heat Source?
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Do most exit signs have tritium?
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Linear transformer driver explanation
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Chernobyl Chernobyl: Options to Limit Reactor Meltdown
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What does the number 0.62 in MCNP refer to?
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How to create a conical source (mamography) in Vgate
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What are the most important parts of the job for a reactor operator?
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Specifying temperatures in MCNP
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What are some expert opinions and advice for buying a dosimeter?
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How to finally run an input file via VISED/MCNP5 without error?
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Heat Transfer Through Cylindrical Nuclear Fuel Pin
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[MCNP6] How to use Tally E with Fmesh
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Can You Cut Geometries in GATE Like in MCNPX?
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Interpretation of Net Peak Area in Gamma Spectroscopy
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Are fusion power plants feasible for widespread use?
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Sound waves inside an inert gas fusion reactor
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What Causes Loss of Particles in a Magnetic Mirror?
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Star Builders: Fusion 30 Years Away?
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Inlet Water Temp vs Feeder Water Temp in a BWR
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Just found out there is strontium in composite dental fillings
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Taishan nuclear reactor Xenon problem
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Leakage in a nuclear condenser
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How Do You Upgrade the MCNP5 Library?
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Fukushima Radiation from blue fin tuna question
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Could a high / very high temperature nuclear reactor operate in Venus?
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Reactor Performance/Design As A Political Ideology
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MCNP4 Trouble -- Zero results with tally type 4
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Hexagonal fuel arrays (VVER and fast reactor fuel)
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Neutron quantity normalization in an eigenvalue computation
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Have you seen this stunning 3D model of a VVER reactor made with Blender 3D?
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MCNP: How to use value zero in a fully specified fill
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Are there any inherent advantages of using He3-He3 over d-He3?
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Xenon poisoning (negative xenon load varies with core burnup)
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Nuclear Power Usage: Hear What Others Know.
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Are fluorescent dyes radioactive?
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Tidal Wave generated by Nuclear Weapon
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3D model I made of the Fukushima Daiichi control room
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Have you heard about the French Fusion Reactor?
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How to Calculate Absolute Gamma Probability from Relative Intensities?
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NRC Event Report SCRAM Code help
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Point Kinetics for Linear Insertion of Reactivity
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MNCP5 error: Program Exception - stack overflow
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Is my used Geiger counter radioactive?
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What is FOGBANK and its role in the US nuclear arsenal?
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Could directed energy revolutionize hybrid heating systems in tokamaks?
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[Fusion] Basic concept behind the Stellarator
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3D model I made of the Three Mile Island control room
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MCNP 6.2: Fission Product Recoil/Transport
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Using a minimized nuclear reactor for further space travel
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Can Flame Jets Effectively Constrain Plasma in Fusion Reactors?
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Is MCNP capable of scoring fission spectrum?
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