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In Brief about Reactor Physics Department(PDF)
Research Areas
- Reactor Physics
- Plasma Physics
- Medical Physics
- Physics of Semiconductors
Department F8 as your Business Partner
Projects
Computer programs
Gallery
Department Staff
Links
Informations for Students
From the History of Department
Contacts


"Jožef Stefan" Institute
Reactor physics department  (F8)
Jamova cesta 39
SI-1000 Ljubljana
Slovenia, EU
Telephone: +386 1 588 5450
Fax: +386 1 588 5377

Department is located at
Reactor Centre Podgorica
.

Head Assistant Prof. Dr. Luka Snoj.

shuffle

Computer Programs Developed at Reactor Physics Department


[CORD2, GNOMERSHUFFLE, FARLOADF, TRIGLAV, TRIGAP, TRIGAC, ...]

CORD2 (IAEA1226)
CORD-2 is intended for core design applications of pressurised water reactors. The main objective was to
assemble a core design system which could be used for simple calculations (such as frequently required
for fuel management) as well as for accurate calculations (for example, core design after refuelling).

Available from Nuclear Energy Agency (NEA) Data Bank Computer Program Services.

See also CORD2 home page.


GNOMER (IAEA1271, RSIC CODE PACKAGE CCC-625)
GNOMER is a program which solves the multigroup neutron diffusion equation in 1D, 2D and 3D cartesian
geometry. The program is designed to calculate the global core power distributions (with thermohydraulic
feedbacks), as well as power distributions and homogenized cross sections over a fuel assembly.

Available from Nuclear Energy Agency (NEA) Data Bank Computer Program Services.
Available from Radiation Safety Information Computational Center (RSICC).

See also GNOMER home page.


TRIGLAV (IAEA1370)
A computer program for reactor calculations of mixed cores in TRIGA Mark II research reactor. It can be
applied for fuel element burn-up calculations, for power and flux distributions calculations and for
reactivity predictions.

Available from Nuclear Energy Agency (NEA) Data Bank Computer Program Service.
See also TRIGLAV home page.


TRIGAC (IAEA1214)
TRIGAP (RSIC CODE PACKAGE CCC-600)
Program for calculating in cylindrical geometry flux and power distributions and burn-up of fuel elements
in TRIGA reactors, taking into account temperature and xenon corrections. Temperature correction can be
either linear, which is applicable for forced cooling, or of second order, which is used for natural
convection.

Available from Nuclear Energy Agency (NEA) Data Bank Computer Program Services.
Available from Radiation Safety Information Computational Center (RSICC).



LOADF
Certain  reactor core parameters are not available to the reactor operator because they are difficult
(or impossible) to measure. They can be provided by calculations, running on-line and simulating the operation
of the reactor. This is the main purpose of the LOADF package.
Windows version is also available.

DMR043
Digital reactivity DMR043 was designed on a PC computer. Numerical algorithms allowing the full
non-homogeneous form of the point kinetics equations to be modelled.
It is used at start-up tests at the Krsko NPP.

SHUFFLE
rogram package SHUFFLE was developed at "Jozef Stefan" Institute for preparing and monitoring the fuel
loading operation at Kr{ko nuclear power plant. Using the package, planning and reloading operation is
easier and safer. The program can create, edit and check steps in the shuffling plan. Summary about
number and type of fuel elements at any location is generated. Program monitors fuel shuffling during
reloading and compares it with the plan.

See also SHUFFLE home page.
Windows version is also available.



FAR
Software package FAR (Fuel Assembly Register), developed at "J. Stefan" Institute, covers all aspects
of the nuclear material accounting on a nuclear facility. FAR was originally designed for the
Krsko NPP but, because of the generality in programming and modularity in structure, can be easily applied
to any other nuclear facility. The main purpose of the package is to simplify control and updating of the fuel
elements properties during NPP lifetime. Automatic data processing reduces possibility of errors and enables
simpler implementation of a QA programme.

See also FAR home page.



TRISTAN (IAEA1337)
A computer program for calculating steady-state axial temperature distribution and flow velocity through
a vertical coolant channel in low power TRIGA reactor core, cooled by natural circulation.

Available from Nuclear Energy Agency (NEA) Data Bank Computer Program Services.



PULSTRI (IAEA1228)
A computer program for mixed core TRIGA Reactor pulse calculations (maximum temperature, prompt energy,
peak power).

Available from Nuclear Energy Agency (NEA) Data Bank Computer Program Services.



TEMPUL (IAEA1338)
A computer program for temperature distribution calculations in fuel element after the pulse.

Available from Nuclear Energy Agency (NEA) Data Bank Computer Program Services.


CEBIS (IAEA0920)
CEBIS is a reactor physics code for calculations of multiplication factor, flux and power distributions
in one dimensional cartesian, cylindrical and spherical geometry. It is intended for reactor physics
calculations of stationary thermal multipying systems in two group diffusion approximation. Besides the
direct solution, the program gives also the adjoint solution of the diffusion equation.

Available from Nuclear Energy Agency (NEA) Data Bank Computer Program Services.


FASVER (IAEA0835)
FASVER2 solves the two-group two dimensional (x-y geometry) stationary diffusion equation of reactor
physics. It is designed for the octant geometry of a typical PWR core with reflector. The adjoint
equation may also be solved.
FASVER4 performs the same calculations as FASVER2, but for one quadrant geometry of a PWR core.

Available from Nuclear Energy Agency (NEA) Data Bank Computer Program Services.



ENDSAM (NEA-1895)
A code for random sampling and validation of covariance data of resonance parameters in ENDF-6 format.
ENDSAM from a nuclear data library file of a chosen isotope in ENDF-6 format produces an arbitrary number
of new files in ENDF-6 format which contain values of randomly sampled resonance parameters
(in accordance with corresponding covariance matrices) in places of original values.

Available from Nuclear Energy Agency (NEA) Data Bank Computer Program Services.


New (March-2017) cross reference table of ORIGIN OF NUCLIDE DATA is available here:
ORIGIN OF NUCLIDE DATA


New (May-2017) home page of new research reactor simulator is available here:
Home page of The research reactor simulator

The research reactor simulator is a fast and robust PC based simulator of a small pool type research reactor developed for the purpose of:

  •     Education of students in reactor physics at institutions with no or limited access to real research reactor
  •     Class-room presentation of RR experiments prior to the real reactor exercises
  •     Preparation prior to exercises on real reactor for more efficient use of time at the real reactor
  •     Train future reactor operators in reactor physics and research reactor operation

See also WLUP Home Page for WIMS related programs (WILLIE) and libraries.

Last edited: 08-Nov-2012 by f8webmaster@ijs.si