Do you know any code for reactor physics study ?
Could you elaborate a bit on what field/aspect you're interested in ?
Like PerennialII mentioned, what exactly do you want to do?
There are commercial core simulator packages like SIMULATE-IIIK (from Studsvik-Scandpower), PRESTO, and one package FORMOSA from North Carolina State University, Electric Power Research Center.
SIMULATE-IIIK requrires data from the CASMO lattice code (also from Studsvik), and PRESTO (PRESTO-B for BWRs) is used with CPM (CPM-3) lattice code.
A little background on FORMOSA
- FORMOSA-P Three-Dimensional/Two-Dimensional Geometry Collapse Methodology purchase the article from ANS.
FORMOSA-P may be available for a small fee - a lot less than SIMULATE. I believe PRESTO is obsolete. FORMOSA is developed by the group under Paul Turinsky, who is also head of the Nuclear Engineering Department as NCSU.
One can also do nuclear calculations with MCNP.
Are you interested in LWR cores, Liquid Metal Fast Reactor (LMFRs), GCR/GCFR's or all three types?
Additional information -
PDQ (Group Diffusion Reactor Computation Code)
ANISN (One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering) - http://www-rsicc.ornl.gov/codes/ccc/ccc2/ccc-254.html
DOT/DORT/TORT - (conventional radiation transport codes from RSICC)
Twodant/Threedant/DANTSYS (available from Nuclear Energy Agency (NEA - OECD) or RSICC(IS))
see - http://www.nea.fr/abs/html/ccc-0547.html [Broken]
see - http://www-rsicc.ornl.gov/codes/ccc/ccc5/ccc-547.html
Academic institutions should have access to this package
PHYSOR conference held every 2 years.
PHYSOR2002 - http://physor2002.kaist.ac.kr/ [Broken] - International Conference on the
New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing
PHYSOR2004 - http://www.physor2004.anl.gov/ [Broken] - The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments
PHYSOR2006 - http://www.cns-snc.ca/physor2006/physor2006.html [Broken]
Vendor proprietary reactor core physics packages
PHOENIX/ANC - BNFL/Westinghouse (Alpha/Phoenix/ANC) for PWRs
TGBLA-6/PANACEA-11 - GE/GNF for BWRs
WIMS/ PANTHER - British Energy/Tractebel.for PWR - see [URL [Broken] OF WIMS/PANTHER CALCULATIONS WITH
MEASUREMENT ON A RANGE OF OPERATING PWR[/url] pdf
PHOENIX/POLCA-7 or CASMO-4/POLCA-7 for BWRs - see VTT- http://www.vtt.fi/inf/pdf/symposiums/2003/S230.pdf
How i can get Registered version of Reactor code MCNP to utilize it for research purposes?
One should be able to obtain MNCP from Radiation Shielding Information Computational Center (RSICC) or OECD-Nuclear Energy Agency (NEA).
One must request the code. However, access may be restricted to academic and scientific institutions.
I am a novice, then I care about some free codes for students. I am caring about some code to compute reactor physics like neutron distribution, lattice calculation, thermohydro calculation ... Thanks for the above news, anyway.
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