B&J NUCLEAR ltd.

„ Atom should be a worker, not a soldier."
I. V. Kurchatov

Our company established in 2013 is specialising in criticality safety simulations and radiation shielding design. Moreover we provide radon measurements with active and passive detectors.

About Team

The core company scientific employees comprise 1 assoc. prof., 2 PhDs and 3 MScs educated and experienced in the field of nuclear power engineering (neutronic core analyses, dosimetry measurements and development of new software solutions). The staff is periodically trained in nuclear fuel fundamentals and power engineering, fast modular reactor core physics, safety assessment of VVERR/PWR with advanced safety features, nuclear project management and economic aspects of a new nuclear power program within training courses and regional workshops. Our workers are certified users of the SCALE system. The company is registered and has access to NEA Data Bank Computer Program Services and has been actively using the available computation tools for R&D in the field of nuclear power engineering. Since early 2017, our company has established and applied a Quality Management System for R&D in natural and technical sciences – nuclear power engineering according to ISO 9001:2015. During projects, the team expanded and the experts from universities or research institutions active in the area of reactor physics, thermal and mechanical engineering or dosimetry supported it.

REFERENCES

Radiation protection

Development of the own design of UAV system for measurement of radiation level during the emergency situations for Slovak NPP provider Slovenske elektrarne a.s.

Reactor physics

The higher harmonics neutron flux modes analysis made for Korea Atomic Energy Research Institute.

Radiation shielding

Precise calculation of effective doses under the modified thermal shield of VVER-440 performed for Slovak NPP provider ENEL as.

Areas of expertise

Criticality safety

A detailed and precise KENO6 3D model of the VVER-440/V213 reactor has been developed for criticality calculations based on available NPP documentation. A tracking system of fuel assembly-wise information (thermal power, boric acid concentration, coolant temperature) was developed to define computational steps for criticality and depletion calculations. Both types of cross-section libraries (CE or MG) can be used where all corresponding data processes are validated and compared to experimental data. Similarity assessment method is standardly used therefore the uncertainty induced by cross-sections and the computational bias can be determined for each criticality calculation.

Shielding analysis

A detailed and precise 3D model of the VVER-440/V213 reactor (including important structural parts of the reactor cavity) has been developed for shielding calculations based on NPP’s documentation. Neutron and gamma detector responses (fluxes or effective/equivalent dose rates) can be determined based on previous criticality and depletion calculations or based on exact source definition. Due to the application of the fixed-source Monte Carlo code with an automated variance reduction technique, a large area can be investigated, or very low statistical uncertainty can be achieved.

Fuel behavior during irradiation

The unique burnup modelling approach has been developed based on a parametric study of VVER-440 fuel (depletion parameters, operation history, assembly type, Gadolinium presence, used energy group structure and time steps) to determine the isotopic composition of the fuel assemblies during reactor operation. Codes for determination of fuel temperature distribution, pellet cladding interaction and fission gas released are developed and implemented into the company computational system to cover complex characterization of the fuel behaviour during operation.

Radiation protection

The Radiation Monitoring System (RMS) has been developed to provide dose rate measurement, air sampling and radiation map creation without requiring human personnel to be present at the measurement site. Individual modules of RMS have been designed to operate with UAV without influencing functionality of each component, to provide sufficient information for the dosimetry staff and to achieve a high standard of reliability. The main key features of the RMS are the modularity, the custom independent in-house control software, the possibility to hibernate and subsequently activate the system upon specific incentives, the easy-to-wipe anti-contamination layer of sensors and the compatibility with various UAV carriers.

Core management analyses

Core employees are actively cooperating, as external advisors, with the National Regulatory Authority of Slovak Republic in the field of the assessment of neutron-physical characteristics and implementation of system codes to the assessment process for VVER-440 reactors.

Research and development

R&D activities are primarily focused on the enhancement of the knowledge in area of application, improvement of defined approaches and support of standardized codes.

B&J NUCLEAR ltd.
Lesna ulica 145/14
90042 Miloslavov
Slovakia

Jakub Lüley
+421 903 252 758
jakub.luley@bjnuclear.eu

Branislav Vrban
+421 907 328 731
branislav.vrban@bjnuclear.eu

www.bjnuclear.eu
info@bjnuclear.eu

B&J NUCLEAR ltd.

„ Atom should be a worker, not a soldier." I. V. Kurchatov

About Team

REFERENCES

Radiation protection

Reactor physics

Radiation shielding

Areas of expertise

Criticality safety

Shielding analysis

Fuel behavior during irradiation

Radiation protection

Core management analyses

Research and development

B&J NUCLEAR ltd. Lesna ulica 145/14 90042 Miloslavov Slovakia Jakub Lüley +421 903 252 758 jakub.luley@bjnuclear.eu Branislav Vrban +421 907 328 731 branislav.vrban@bjnuclear.eu www.bjnuclear.eu info@bjnuclear.eu

„ Atom should be a worker, not a soldier."
I. V. Kurchatov

B&J NUCLEAR ltd.
Lesna ulica 145/14
90042 Miloslavov
Slovakia

Jakub Lüley
+421 903 252 758
jakub.luley@bjnuclear.eu

Branislav Vrban
+421 907 328 731
branislav.vrban@bjnuclear.eu

www.bjnuclear.eu
info@bjnuclear.eu