Editing Neutron transport (section)

===Computer codes used in neutron transport===

====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>

====Deterministic codes====
*''Ardra'' – A [[Lawrence Livermore National Laboratory|LLNL]] neutral particle transport code <ref>{{cite web|title=Ardra|url=https://computing.llnl.gov/projects/ardra-scaling-up-sweep-transport-algorithms}}</ref>
*''Attila'' – A commercial transport code
*''DRAGON'' – An open-source lattice physics code
*''PHOENIX/ANC'' – A proprietary lattice-physics and global diffusion code suite from [[Westinghouse Electric Corporation|Westinghouse Electric]]
*''PARTISN'' – A [[Los Alamos National Laboratory|LANL]] developed transport code based on the discrete ordinates method<ref>{{Cite web |title=RSICC CODE PACKAGE CCC 760 |url=https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-842.html |access-date=2022-08-05 |website=rsicc.ornl.gov}}</ref>
*''NEWT'' – An [[Oak Ridge National Laboratory|ORNL]] developed 2-D S<sub>N</sub> code <ref name=":0">{{Cite web |title=SCALE Overview {{!}} ORNL |url=https://www.ornl.gov/scale/overview |access-date=2022-08-05 |website=www.ornl.gov}}</ref>
*''DIF3D/VARIANT'' – An Argonne National Laboratory developed 3-D code originally developed for fast reactors <ref>{{Cite web |title=Software: DIF3D – Nuclear Engineering Division (Argonne) |url=https://www.ne.anl.gov/codes/dif3d/ |access-date=2022-08-05 |website=www.ne.anl.gov}}</ref>
*''DENOVO'' – A massively parallel transport code under development by [[Oak Ridge National Laboratory|ORNL]]<ref name=":0" /><ref>{{Cite journal |last1=Evans |first1=Thomas M. |last2=Stafford |first2=Alissa S. |last3=Slaybaugh |first3=Rachel N. |last4=Clarno |first4=Kevin T. |date=2010-08-01 |title=Denovo: A New Three-Dimensional Parallel Discrete Ordinates Code in SCALE |url=https://doi.org/10.13182/NT171-171 |journal=Nuclear Technology |volume=171 |issue=2 |pages=171–200 |doi=10.13182/NT171-171 |bibcode=2010NucTe.171..171E |s2cid=93751324 |issn=0029-5450|url-access=subscription }}</ref>
*''Jaguar'' – A parallel 3-D [[Slice Balance Approach]] transport code for arbitrary polytope grids developed at [[Knolls Atomic Power Laboratory|NNL]]<ref>{{cite book |last1=Watson |first1=A. M. |last2=Grove |first2=R. E. |last3=Shearer |first3=M. T. |title=Effective software design for a deterministic transport system |date=2009 |publisher=American Nuclear Society |isbn=978-0-89448-069-0 |url=https://inis.iaea.org/search/searchsinglerecord.aspx?recordsFor=SingleRecord&RN=42064864 |access-date=5 August 2022}}</ref>
*''DANTSYS''
*''RAMA'' – A proprietary 3D [[method of characteristics]] code with arbitrary geometry modeling, developed for [[Electric Power Research Institute|EPRI]] by TransWare Enterprises Inc.<ref>{{cite web|title=RAMA|url=http://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML050750478}}</ref>
*''RAPTOR-M3G'' – A proprietary parallel radiation transport code developed by [[Westinghouse Electric Company]]
*''OpenMOC'' – An [[Massachusetts Institute of Technology|MIT]] developed open source parallel [[method of characteristics]] code<ref>{{cite web|title=OpenMOC|url=https://mit-crpg.github.io/OpenMOC/}}</ref>
*''MPACT'' – A parallel 3D [[method of characteristics]] code under development by [[Oak Ridge National Laboratory]] and the [[University of Michigan]]
*''DORT'' – Discrete Ordinates Transport
*''APOLLO'' – A lattice physics code used by [[French Alternative Energies and Atomic Energy Commission|CEA]], [[Électricité de France|EDF]] and [[Areva NC|Areva]]<ref>{{cite web|title=APOLLO3|url=http://mathematicsandcomputation.cowhosting.net/MC09/pdfs/201216.pdf|access-date=2015-08-29|archive-url=https://web.archive.org/web/20151222075936/http://mathematicsandcomputation.cowhosting.net/MC09/pdfs/201216.pdf|archive-date=2015-12-22|url-status=dead}}</ref>
*''CASMO/SIMULATE'' – A proprietary lattice-physics and diffusion code suite developed by [[Studsvik]] for [[Light-water reactor|LWR]] analysis including square and hex lattices<ref>{{cite web|title=CASMO5|url=https://www.studsvik.com/testing-new-web/start2/testing-new-web2/start/business/products/casmo/
}}</ref>
*''HELIOS'' – A proprietary lattice-physics code with generalized geometry developed by [[Studsvik]] for [[Light-water reactor|LWR]] analysis<ref>{{cite web|title=CASMO5|url=https://www.studsvik.com/testing-new-web/start2/testing-new-web2/start/business/products/helios/
}}</ref>
*''milonga'' – A free nuclear reactor core analysis code<ref>{{cite web|title=Milonga|url=https://www.seamplex.com/milonga}}</ref>
*''STREAM'' –  A neutron transport analysis code, STREAM (Steady state and Transient REactor Analysis code with Method of Characteristics), has been developed since 2013 at Ulsan National Institute of Science and Technology (UNIST), Republic of Korea <ref>{{cite web|title=STREAM|url=http://reactorcore.unist.ac.kr/stream/}}</ref>