Editing Neutron transport (section)

====Probabilistic codes====
*''COG -'' A LLNL developed Monte Carlo code for criticality safety analysis and general radiation transport (<nowiki>http://cog.llnl.gov</nowiki>)
*''MCBEND'' <ref>{{cite web|title=MCBEND|url=https://www.answerssoftwareservice.com/mcbend/}}</ref> – A Monte Carlo code for general radiation transport developed and supported by the ANSWERS Software Service.<ref name="ANSWERS">{{cite web|title=ANSWERS|url=https://www.answerssoftwareservice.com/}}</ref>
*''[[MCNP]]'' – A [[Los Alamos National Laboratory|LANL]] developed Monte Carlo code for general radiation transport
*MC21<ref>{{Cite report |url=https://www.osti.gov/biblio/903083 |title=The MC21 Monte Carlo Transport Code |date=2007-01-09 |publisher=Knolls Atomic Power Lab. (KAPL), Niskayuna, NY (United States) |issue=LM-06K144 |osti=903083 |language=English}}</ref> – A general-purpose, 3D Monte Carlo code developed at [[Knolls Atomic Power Laboratory|NNL]].
*''MCS'' – The Monte Carlo code MCS has been developed since 2013 at Ulsan National Institute of Science and Technology (UNIST), Republic of Korea.<ref>{{cite web|title=MCS|url=http://reactorcore.unist.ac.kr/mcs/}}</ref>
*''Mercury'' – A [[Lawrence Livermore National Laboratory|LLNL]] developed Monte Carlo particle transport code.<ref>{{cite web|title=Mercury|url=https://wci.llnl.gov/simulation/computer-codes/mercury}}</ref>
*''MONK'' <ref>{{cite web|title=MONK|url=https://www.answerssoftwareservice.com/monk/}}</ref> – A Monte Carlo Code for criticality safety and reactor physics analyses developed and supported by the ANSWERS Software Service.<ref name="ANSWERS" /> 
*''MORET'' – Monte-Carlo code for the evaluation of criticality risk in nuclear installations developed at IRSN, France<ref>{{cite web|title=MORET5|url=https://www.irsn.fr/EN/Research/Scientific-tools/Computer-codes/Pages/Moret-Code.aspx}}</ref>
*''OpenMC'' – An open source, community-developed open source Monte Carlo code<ref>{{cite web|title=OpenMC|url=https://docs.openmc.org/}}</ref>
*''RMC'' – A [[Tsinghua University]] Department of Engineering Physics developed Monte Carlo code for general radiation transport
*SCONE – The '''S'''tochastic '''C'''alculator '''O'''f the '''N'''eutron Transport '''E'''quation, an open-source Monte Carlo code developed at the University of Cambridge.<ref>{{Cite web |title=SCONE |url=https://github.com/CambridgeNuclear/SCONE |website=[[GitHub]]}}</ref>
*''[[Serpent (software)|Serpent]]'' – A [[VTT Technical Research Centre of Finland]] developed Monte Carlo particle transport code<ref>{{cite web|title=Serpent – A Monte Carlo Reactor Physics Burnup Calculation Code|url=http://montecarlo.vtt.fi/|access-date=2013-12-03|archive-url=https://web.archive.org/web/20140901002129/http://montecarlo.vtt.fi/|archive-date=2014-09-01|url-status=dead}}</ref>
*''Shift/KENO'' – [[Oak Ridge National Laboratory|ORNL]] developed Monte Carlo codes for general radiation transport and criticality analysis
*''TRIPOLI'' – 3D general purpose continuous energy Monte Carlo Transport code developed at CEA, France<ref>{{cite web|title=TRIPOLI-4|date=19 October 2013|url=http://www.cea.fr/nucleaire/tripoli-4}}</ref>
*''UCN'' - Monte Carlo transport code for simulating experiments with ultracold neutrons developed at PNPI, Gatchina<ref>{{cite journal | last1=Fomin | first1=A.K. | last2=Serebrov | first2=A.P. | title=Monte Carlo Model of the Experiment on Measuring the Neutron Lifetime | journal=Mathematical Models and Computer Simulations | volume=10 | issue=6 | year=2018 | doi=10.1134/S2070048218060066 | pages=741–747}}</ref>