Projects / Programmes
January 1, 2004
- December 31, 2008
| Code |
Science |
Field |
Subfield |
| 2.03.00 |
Engineering sciences and technologies |
Energy engineering |
|
| 1.07.00 |
Natural sciences and mathematics |
Computer intensive methods and applications |
|
| Code |
Science |
Field |
| T160 |
Technological sciences |
Nuclear engineering and technology |
| P170 |
Natural sciences and mathematics |
Computer science, numerical analysis, systems, control |
reactor physics, nuclear data, global reactor calculations, Monte Carlo, radiation treatment planning
Researchers (11)
Organisations (1)
| no. |
Code |
Research organisation |
City |
Registration number |
No. of publicationsNo. of publications |
| 1. |
0106 |
Jožef Stefan Institute |
Ljubljana |
5051606000 |
90,649 |
Abstract
Research is performed in the following areas:
- nuclear data evaluation,
- development of new methods for reactor calculations,
- numerical modelling of reactor processes,
- Monte Carlo modelling of demanding geometries,
- and, as a spin-off, use of Monte Carlo methods for inverse treatment planning in medicine.
Nuclear data evaluation comprises compilations, evaluation and maintenance of modern data libraries (ENDFB-6, JENDL). This is performed in order to develop and maintain our own database for both fission and fusion systems calculations. Research is performed also on both theoretical and experimental benchmark problems. Work on an international project WLUP (WIMS Library Updating Project) is continued.
Development of new methods for reactor calculations is centered on those parts of global reactor calculations which are computationally intensive. For diffusion approximation this means the calculation of effective group homogenized macroscopic constants depending on parameters such as temperature or burnup. On the other hand, for transport problems, this means the calculation of group macroscopic crossections averaged over true neutron spectrum within a group. This enables us to attain higher efficiency on precision of the transport calculation in depth of the transport medium. Research results will be incorporated into our program package CORD which is used for NPP Krško core designing and into transport code DORT, which is used for activation calculations of the NPP Krško and TRIGA biological shield.
Computational modelling will cover the research into nuclear fuel burnup and also activation of reactor components. Primary goal is to ammeliorate burnup models in basic reactor computer codes in order to be able to verify them with experimental data obtained from the measurements on the TRIGA reactor. Method for reactor activation calculations will be expanded in order to cover the activation of metallic component for both experimental and power reactors.
Using Monte Carlo methods, we will continue with preparation and calculation of both research and power reactor benchmarks. We intend to use various versions of MCNP code together with ENDFB-6 crossection data. We will study variance reduction methods (DSA and WW) in demanding reactor geometries, aimed to precise determination of biological shield and metallic reactor parts activation.
We will continue the development of the inverse treatment planning in medicine (oncology). This method is very promising and is already being clinically implemented in spite of being highly computationally demanding. Research will be performed together with University of Wisconsin, Madison, USA.
Significance for science
Research program was concieved to cover all aspects of reactor physics and to be complementary with intense research elsewhere. Results are therefore interesting on international scale and were published in relevant scientific literature. We have seen interest in our work in the following domains: - nuclear data bases verification, - experimental benchmarks analysis, - neutron activation studies in fission and fusion systems, - Monte Carlo studies of experimental and power reactors, - use of Monte Carlo methods for radiation treatment planning.
Significance for the country
Existence of the reactor physics research group is an essential element of nuclear safety system in Slovenia, since the members of this research group also work as experts in the system of nuclear safety assurance according to european and United nations directives. Senior members of the research group are - all of them - also faculty staff at four departments on three slovenian universities. Through their additional pedagogical work they cover all slovenian needs for new cadre formation.
Most important scientific results
Final report,
complete report on dLib.si
Most important socioeconomically and culturally relevant results
Final report,
complete report on dLib.si
