Projects / Programmes
January 1, 2009
- December 31, 2013
| 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 |
| Code |
Science |
Field |
| 2.11 |
Engineering and Technology |
Other engineering and technologies |
reactor physics, nuclear data, global reactor calculations, Monte Carlo, radiation treatment planning
Researchers (21)
Organisations (2)
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
Future operation of the JET tokamak depends, amongst other factor, also on proper measurement of neutron yield, which has to be within the operational range. All scientific projects require meaningful results of the neutron yield measurements for the characterization of individual pulses. Verification of neutron measurement is important also for the future operation in the D-D and D-T mode. Application and development of experimental and computational methods that we are going to develop will be later extended to the future operation of the D-T mode and will contribute significantly to the activities planned in JET tokamak. The whole process of understanding and improving the knowledge of the neutron yield measurements is also important for the future fusion reactor ITER, where the methods for the calibration of neutron detectors are yet to be determined. Accurate knowledge of the reactor’s fusion power, which can be measured only through the neutron measurements, is extremely important for the development of fusion as a sustainable and environmentally friendly source of energy. Evaluated results of the experiment will serve as a reference experiment for the verification and validation of computational methods and nuclear data in fusion tokamaks and other similar systems, such as conventional fission reactors, which have similar materials and virtually the same detectors. Reference model will be used for the verification and validation of Monte Carlo variance reduction methods and for the validation of nuclear data libraries.
Significance for the country
The knowledge obtained and the experience gained will be directly applicable to the Slovenian Nuclear Power Plant Krško. The results of our research will be used for: • determination of the nuclear detectors response function in classical fission reactors, which is important for accurate and reliable reactor operation and determination of reactor measured parameters, • accuracy improvements in the determination of the vessel irradiation fluence, which is of paramount importance for the determination of reactor life time and possible life extension, • accuracy improvements in the determination of material activation outside the reactor vessel, which is important for the determination of radioactive waste during the plant decommissioning. In power reactors the direct calibration of thermal power with well-defined sources (such as Cf-252) is nearly impossible because of practical and financial limitations. Research reactors are too small and not simple to be a representative substitute. Therefore knowledge and experience gained on experimental fusion reactors are invaluable also for classical fission reactors.
Most important scientific results
Annual report
2009,
2010,
2011,
2012,
final report,
complete report on dLib.si
Most important socioeconomically and culturally relevant results
Annual report
2009,
2011,
2012,
final report,
complete report on dLib.si
