Krešimir Trontl

Krešimir Trontl
University of Zagreb · Department of Applied Physics (ZPF)

About

28
Publications
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75
Citations

Publications

Publications (28)
Article
Full-text available
Nuclear energy is an option that enables a significant reduction of greenhouse gases emissions at the national and European Union (EU) level. However, it is also an option that is mostly influenced by public opinion and an option that has strong cross-border impact. Croatia does not consider nuclear options, but a possible future turn to nuclear mi...
Article
Radioactive waste management is a demanding problem that is raising tensions and misunderstanding amongst the general public, experts, and policy makers in a number of countries. An investigation into the public opinion, legal framework, policy, and expert involvement on the matter of radioactive waste management has been performed in Croatia. The...
Article
Full-text available
In recent years, most of the growth in electricity demand is covered by renewable and nuclear energy sources. However, electricity generation in fossil-fired power plants is also increasing resulting in the increase of CO2 emissions. Nuclear energy has to be considered as one of the available tools to accomplish CO2 emission reduction in electricit...
Article
Full-text available
The capabilities of the SCALE6.1/MAVRIC hybrid shielding methodology (CADIS and FW-CADIS) were demonstrated when applied to a realistic deep penetration Monte Carlo (MC) shielding problem of a full-scale PWR containment model. Automatic preparation of variance reduction (VR) parameters is based on deterministic transport theory ( SN method) providi...
Article
The PWR biological shield concrete activation is analyzed using SCALE6.1 hybrid deterministic–stochastic shielding methodology. Since accurate geometry representation is a paramount step for this type of shielding calculation involving heterogeneous three dimensional regions (reactor core, thermal shield, downcomer, pressure vessel, cavity, and shi...
Conference Paper
The SCALE6.1/MAVRIC hybrid deterministic-stochastic shielding methodology was used for dose rates calculation of the generic spent fuel dry storage installation. The neutron-gamma dose rates around the cask array were calculated over a large problem domain in order to determine the boundary of the controlled area. The FW-CADIS methodology, based on...
Conference Paper
Full-text available
Increase in electricity demand, need to fulfill the so called " 20-20-20 " requirements, as well as the relatively adequate legislative framework, resulted in an increase of the renewable energy sources (RES) integration in the Croatian power system, especially observed during the last decade. However, due to the intermittent RES characteristics hi...
Conference Paper
The PWR biological shield concrete activation is analyzed using SCALE6.1 hybrid deterministic-stochastic shielding methodology. Since accurate geometry representation is a paramount step for this type of shielding calculation involving heterogeneous three dimensional regions (reactor core, thermal shield, downcomer, pressure vessel, cavity, and shi...
Article
The SCALE6.0 simulation model of a typical PWR primary loop components for effective dose rates calculation based on hybrid deterministic–stochastic methodology was created. The criticality sequence CSAS6/KENO-VI of the SCALE6.0 code package, which includes KENO-VI Monte Carlo code, was used for criticality calculations, while neutron and gamma dos...
Conference Paper
The capabilities and limitations of SCALE6/MAVRIC hybrid deterministic-stochastic shielding methodology (CADIS and FW-CADIS) are demonstrated when applied to a realistic deep penetration Monte Carlo (MC) shielding problem of full-scale PWR containment model. The ultimate goal of such automatic variance reduction (VR) techniques is to achieve accept...
Conference Paper
A 3D simulation model of typical pressurized water reactor (PWR) primary loop components for effective dose rates calculation based on hybrid deterministic-stochastic methodology was created. Shielding calculations have been performed using MAVRIC shielding sequence of SCALE6.0 code package. A detailed model of a combinatorial geometry, materials a...
Article
Full-text available
Revised guidelines with the support of computational benchmarks are needed for the regulation of the allowed neutron irradiation to reactor structures during power plant lifetime. Currently, US NRC Regulatory Guide 1.190 is the effective guideline for reactor dosimetry calculations. A well known international shielding database SINBAD contains larg...
Conference Paper
The Gas-Cooled Fast Reactor (GFR) is one of the reactor concepts selected by the Generation IV International Forum (GIF) for the next generation of innovative nuclear energy systems. It was selected among a group of more than 100 prototypes and his commercial availability is expected by 2030. GFR has common goals as the rest GIF advanced reactor ty...
Chapter
In this chapter, we consider the application of Support Vector Regression (SVR) in the field of radiation dose rate calculations, namely, determination of gamma ray dose buildup factors. We demonstrate that the SVR model for buildup factor determination can be applied as a fast engineering tool, replacing more traditional approaches based on semi-e...
Article
When discussing the computer programming education at university level, one is usually focused on education of future computer science experts, while the computer education of technical engineers is put aside. Technical engineers are mostly trained in using commercial software specific for their area of expertise. However, due to somewhat extreme s...
Article
Full-text available
The usual approach to loading pattern optimization involves high degree of engineering judgment, a set of heuristic rules, an optimization algorithm, and a computer code used for evaluating proposed loading patterns. The speed of the optimization process is highly dependent on the computer code used for the evaluation. In this paper, we investiga...
Article
The accuracy of the point-kernel method, which is a widely used practical tool for γ-ray shielding calculations, strongly depends on the quality and accuracy of buildup factors used in the calculations. Although, buildup factors for single-layer shields comprised of a single material are well known, calculation of buildup factors for stratified shi...
Conference Paper
The intention was to model a dry storage facility that could satisfy the needs of a medium nuclear power plant similar to the NPP Krsko. The attention has been focused on radiation dose rate analyses and criticality calculations. Using the SCALE 4.4 code package and modified QAD-CGGP code, we modeled a facility that satisfies the basic criteria for...
Article
Full-text available
The aim of this paper is to evaluate dose rates for a hypothetical accident with transport package containing Iridium-192 source and to design additional shielding necessary for the safe unloading of the container, assuming that during the unloading process the whole contents of a radioactive source is unshielded and that the operation is going to...
Article
Full-text available
The objective of the research reported in this paper was to evaluate the feasibility and costs of ultra-long operating cycles in existing pressurized water reactors while respecting current fuel burnup limits. Using the FUMACS/FEEC 2001 code package, a core design for a single batch ultra-long (36 month) operating cycle has been developed. An addit...
Article
Full-text available
Using the SCALE-4 code package we have analyzed double tiering as an option of the NPP Krško spent fuel pool capacity increase. Both, criticality of the spent fuel pool expressed through multiplication factor value, as well as the gamma and neutron dose rates in the vicinity of the spent fuel pool have been calculated and compared to the values of...
Article
Full-text available
The Gas-cooled Fast Reactor (GFR) is one of the reactor concepts selected by the Generation IV International Forum for the next generation of innovative nuclear energy systems. Several GFR fuel design concepts such as plates, rod pins, and pebbles are currently being investigated. At the same time, various codes are being tailored and developed for...
Article
Full-text available
Results of the 2007/08 survey "Energy – the present and the future" conducted on a population of 1439 students from Zagreb University have shown that after school and television, internet is the third major source of knowledge for the participants. Therefore, "NEMIS" web site (www.nemis.zpf.fer.hr) was launched at the end of the 2008. NEMIS is a Cr...
Article
Full-text available
Three-dimensional Monte Carlo computer code KENO-VI of CSAS26 sequence of SCALE-4.4 code system was applied for pin-by-pin calculations of the effective multiplication factor for the first cycle IRIS reactor core. The effective multiplication factors obtained by the above mentioned Monte Carlo calculations using 27-group ENDF/B-IV library and 238-g...
Article
Full-text available
Recent activities focused on spent fuel management in the NPP Krško led to the spent fuel pool capacity increase by reracking. In this paper we have investigated the reracking impact on radiation dose rates in the vicinity of the spent fuel pool at the end of the plant lifetime. Real case scenario of spent fuel pool loading has been assumed by taki...

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