"Jožef Stefan" Institute
Reactor physics department (F8)
Jamova cesta 39
SI1000 Ljubljana
Slovenia, EU
Telephone: +386 1 588 5450
Fax: +386 1 588 5377
Department is located at
Reactor Centre Podgorica.
Head Assoc. Prof. Dr. Luka Snoj.

Computer Programs Developed at Reactor Physics
Department
[CORD2, GNOMER, SHUFFLE, FAR, LOADF, TRIGLAV, TRIGAP, TRIGAC, ...]
CORD2 (IAEA1226)
CORD2 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
CCC625)
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 burnup 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 CCC600)
Program for calculating in cylindrical geometry flux and
power distributions and burnup 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 online 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
nonhomogeneous form of the point kinetics equations to be
modelled.
It is used at startup 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 steadystate 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 twogroup two dimensional (xy 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 (NEA1895)
A code for random sampling and validation of covariance data
of resonance parameters in ENDF6 format.
ENDSAM from a nuclear data library file of a chosen isotope
in ENDF6 format produces an arbitrary number
of new files in ENDF6 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 (March2017) cross reference table of ORIGIN OF
NUCLIDE DATA is available here:
ORIGIN
OF NUCLIDE DATA
New (May2017) 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
 Classroom 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.
