Developments in Nuclear Field for Developments in Nuclear Field for Education, Industry and MedicineEducation, Industry and Medicine

at theat the

Taras Shevchenko National Taras Shevchenko National University of KyivUniversity of Kyiv

Prof. Dr. Igor KADENKOProf. Dr. Igor KADENKO

Director, International Nuclear Safety Center of Ukraine,Director, International Nuclear Safety Center of Ukraine,

Head, Department of Nuclear Physics and Engineering,Head, Department of Nuclear Physics and Engineering,Taras Shevchenko National University of Kyiv Taras Shevchenko National University of Kyiv

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

Department of Nuclear Physics and EngineeringDepartment of Nuclear Physics and Engineering

OUTLINE OUTLINE of Presentationof Presentation

An analytical approach to the generation of the An analytical approach to the generation of the operational limit curves with NDE based crack postulation.operational limit curves with NDE based crack postulation.

Application of CATHARE code to the investigation of Application of CATHARE code to the investigation of PTS events for VVER NPPs.PTS events for VVER NPPs.

New system “SOKRAT” for WWER-1000 reactor New system “SOKRAT” for WWER-1000 reactor pressure vessel visual survey from outer surface.pressure vessel visual survey from outer surface.

Development of medical image processing algorithms Development of medical image processing algorithms optimized for execution on GPU.optimized for execution on GPU.

Three-dimensional polymer dosimetry.Three-dimensional polymer dosimetry.Medical physics calculations for Ukrainian hospitals.Medical physics calculations for Ukrainian hospitals.Conclusions.Conclusions.

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

Department of Nuclear Physics and EngineeringDepartment of Nuclear Physics and Engineering

An Analytical Approach to the Generation of the An Analytical Approach to the Generation of the Operational Limit CurvesOperational Limit Curves with NDE Based Crack with NDE Based Crack

PostulationPostulation

The main tasks of the p-T curves generationThe main tasks of the p-T curves generation::Generation of LIMIT A curves;Generation of LIMIT A curves;Verification of cool-down limitations and determination of Verification of cool-down limitations and determination of

the appropriate soak times following a PTS event.the appropriate soak times following a PTS event. The approach has been developed in accordance with The approach has been developed in accordance with

Westinghouse methodology. Westinghouse methodology.

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

LIMIT A GenerationLIMIT A GenerationLIMITLIMIT А А is the curve on is the curve on T-p plane, generated in such a T-p plane, generated in such a

way:way:• the values of pthe values of p and Tand T from the right of LIMIT A do ensure the RPV from the right of LIMIT A do ensure the RPV

integrity from the brittle fracture criterion point of view. integrity from the brittle fracture criterion point of view.

LIMIT A is an envelope of the two curves:LIMIT A is an envelope of the two curves:• ««Step Cooldown Crack Initiation LimitStep Cooldown Crack Initiation Limit»;»;

• «Isothermal Wall Crack Initiation Limit».«Isothermal Wall Crack Initiation Limit».

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

An Analytical Approach to the Generation of the An Analytical Approach to the Generation of the Operational Limit CurvesOperational Limit Curves with NDE Based Crack with NDE Based Crack

PostulationPostulation

Example of LIMITExample of LIMIT АА

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

An Analytical Approach to the Generation of the An Analytical Approach to the Generation of the Operational Limit CurvesOperational Limit Curves with NDE Based Crack with NDE Based Crack

PostulationPostulation

Model transient scenarioModel transient scenario

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

An Analytical Approach to the Generation of the An Analytical Approach to the Generation of the Operational Limit CurvesOperational Limit Curves with NDE Based Crack with NDE Based Crack

PostulationPostulation

Thermoelasticity problem: heat conductionThermoelasticity problem: heat conduction

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

,2

22

x

Ta

t

T kk

k

02

hxt

T

,11

21 hxhxTT

11

22

11

hxhx x

T

x

T

(2)(2)

(1)(1)

(3)(3)

(4)(4)

Initial condition:Initial condition:

EquationEquation 2,1k

),(00

111 tT

x

T

HT

x

Boundary conditions:Boundary conditions:

00 tkT

An Analytical Approach to the Generation of the An Analytical Approach to the Generation of the Operational Limit CurvesOperational Limit Curves with NDE Based Crack with NDE Based Crack

PostulationPostulation

Thermoelasticity problem: stressesThermoelasticity problem: stresses

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

(5)(5)

(6)(6)

021 crrarr

brbruu 21

brrbrr 21

Boundary conditions:Boundary conditions:

An Analytical Approach to the Generation of the An Analytical Approach to the Generation of the Operational Limit CurvesOperational Limit Curves with NDE Based Crack with NDE Based Crack

PostulationPostulation

SIF calculation algorithmSIF calculation algorithmThe SIF calculation has been carried out with the help of The SIF calculation has been carried out with the help of

weight function method. weight function method. The stresses were The stresses were approximated by the following approximated by the following

expressionexpression::

..

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

n

iii )x(f)t(a)t,x(

1

An Analytical Approach to the Generation of the An Analytical Approach to the Generation of the Operational Limit CurvesOperational Limit Curves with NDE Based Crack with NDE Based Crack

PostulationPostulation

Comparison of LIMITComparison of LIMIT АА for crack with a=h/4 for crack with a=h/4

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

An Analytical Approach to the Generation of the An Analytical Approach to the Generation of the Operational Limit CurvesOperational Limit Curves with NDE Based Crack with NDE Based Crack

PostulationPostulation

Comparison of limit p-T curves for soak time determinationComparison of limit p-T curves for soak time determination

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

An Analytical Approach to the Generation of the An Analytical Approach to the Generation of the Operational Limit CurvesOperational Limit Curves with NDE Based Crack with NDE Based Crack

PostulationPostulation

Forming of the Forming of the temperature loadingtemperature loading

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

An Analytical Approach to the Generation of the An Analytical Approach to the Generation of the Operational Limit CurvesOperational Limit Curves with NDE Based Crack with NDE Based Crack

PostulationPostulation

Parameters settingParameters setting

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

An Analytical Approach to the Generation of the An Analytical Approach to the Generation of the Operational Limit CurvesOperational Limit Curves with NDE Based Crack with NDE Based Crack

PostulationPostulation

p-T Curves Data p-T Curves Data DisplayingDisplaying

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

An Analytical Approach to the Generation of the An Analytical Approach to the Generation of the Operational Limit CurvesOperational Limit Curves with NDE Based Crack with NDE Based Crack

PostulationPostulation

Stresses Data Stresses Data DisplayingDisplaying

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

An Analytical Approach to the Generation of the An Analytical Approach to the Generation of the Operational Limit CurvesOperational Limit Curves with NDE Based Crack with NDE Based Crack

PostulationPostulation

Conclusions -1Conclusions -1Pressure-temperature (p-T) Operational Limit Curves are Pressure-temperature (p-T) Operational Limit Curves are

used:used:• to support NPP control room operator actions in response to to support NPP control room operator actions in response to

pressurized thermal shock (PTS) accidents andpressurized thermal shock (PTS) accidents and

• to control the cool-down process after the PTS. to control the cool-down process after the PTS.

The limits defined by p-T curves are determined by the The limits defined by p-T curves are determined by the conditions of initiation of through-wall propagation of the conditions of initiation of through-wall propagation of the crack postulated in the wall of RPV. crack postulated in the wall of RPV.

The generally accepted procedure of p-T curves The generally accepted procedure of p-T curves development is generated by Westinghouse and is based on development is generated by Westinghouse and is based on Finite-Element (FE) fracture mechanics analysis. Finite-Element (FE) fracture mechanics analysis.

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

An Analytical Approach to the Generation of the An Analytical Approach to the Generation of the Operational Limit CurvesOperational Limit Curves with NDE Based Crack with NDE Based Crack

PostulationPostulation

Conclusions-1 Conclusions-1 (cont`d)(cont`d)

In collaboration with Westinghouse Electric (Belgium) we In collaboration with Westinghouse Electric (Belgium) we applied their approach for the development of the p-T curves applied their approach for the development of the p-T curves for all Ukrainian VVER units.for all Ukrainian VVER units.

Using experience we develop the simplification of WOG Using experience we develop the simplification of WOG procedure which is based on the analytical algorithm. procedure which is based on the analytical algorithm.

The validity of the analytically constructed p-T curves is The validity of the analytically constructed p-T curves is proved by the comparison with the results of FE calculations. proved by the comparison with the results of FE calculations.

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

An Analytical Approach to the Generation of the An Analytical Approach to the Generation of the Operational Limit CurvesOperational Limit Curves with NDE Based Crack with NDE Based Crack

PostulationPostulation

Conclusions-1 Conclusions-1 (cont`d)(cont`d)

The original computer program has been developed. The original computer program has been developed. The program makes it possible to develop p-T curves for the The program makes it possible to develop p-T curves for the

VVER-1000 RPV with the options of variation of crack size VVER-1000 RPV with the options of variation of crack size and orientation, neutron fluence value, critical temperature and orientation, neutron fluence value, critical temperature of brittleness value and critical fracture toughness of brittleness value and critical fracture toughness expression.expression.

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

An Analytical Approach to the Generation of the An Analytical Approach to the Generation of the Operational Limit CurvesOperational Limit Curves with NDE Based Crack with NDE Based Crack

PostulationPostulation

CATHARE code was granted by AREVA, EdF, IRSN to International CATHARE code was granted by AREVA, EdF, IRSN to International Nuclear Safety Center of Ukraine of the Taras Shevchenko National Nuclear Safety Center of Ukraine of the Taras Shevchenko National University of Kyiv for the application in the education/research and University of Kyiv for the application in the education/research and using for analytical (not commercial) tasksusing for analytical (not commercial) tasks We study:We study:• Field of Code application;Field of Code application;

• Code structure;Code structure;

• Code elements and appropriate mathematical models;Code elements and appropriate mathematical models;

• Numerical algorithms;Numerical algorithms;

• The simplest model tasks of calculation of the temperature and pressure fields in piping The simplest model tasks of calculation of the temperature and pressure fields in piping and elements.and elements.

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

Application of CATHARE Code to the Investigation Application of CATHARE Code to the Investigation of PTS Events for VVER NPPSof PTS Events for VVER NPPS

An example of CATHARE applicationAn example of CATHARE application

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

Application of CATHARE Code to the Investigation Application of CATHARE Code to the Investigation of PTS Events for VVER NPPSof PTS Events for VVER NPPS

The rupture of hot leg (out-leg GZT) and the injection of the The rupture of hot leg (out-leg GZT) and the injection of the cold water to one of the cold legs: using THREED elementcold water to one of the cold legs: using THREED element

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

Application of CATHARE Code to the Investigation Application of CATHARE Code to the Investigation of PTS Events for VVER NPPSof PTS Events for VVER NPPS

Temperature field in the THREED elementTemperature field in the THREED element

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

Application of CATHARE Code to the Investigation Application of CATHARE Code to the Investigation of PTS Events for VVER NPPSof PTS Events for VVER NPPS

Flow choking in the RUPTIRE element: dependence of gas Flow choking in the RUPTIRE element: dependence of gas fraction on timefraction on time

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

Application of CATHARE Code to the Investigation Application of CATHARE Code to the Investigation of PTS Events for VVER NPPSof PTS Events for VVER NPPS

RPV coolant temperature for different downcomer pointsRPV coolant temperature for different downcomer points

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

Application of CATHARE Code to the Investigation Application of CATHARE Code to the Investigation of PTS Events for VVER NPPSof PTS Events for VVER NPPS

The highest curve corresponds to the point under cold leg without ECC water injection, The highest curve corresponds to the point under cold leg without ECC water injection, three lower curves correspond to the points with different heights under the leg with three lower curves correspond to the points with different heights under the leg with ECC water injection.ECC water injection.

Conclusions -2Conclusions -2CATHARE code is available for University of Kyiv students CATHARE code is available for University of Kyiv students

studying Nuclear Engineering;studying Nuclear Engineering;Even without training received we are capable to learn and Even without training received we are capable to learn and

apply this code to motivate and educate students; apply this code to motivate and educate students; Plans are to further make CATHARE available to study Plans are to further make CATHARE available to study

complex processes in reactor primary circuit. complex processes in reactor primary circuit.

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

Application of CATHARE Code to the Investigation Application of CATHARE Code to the Investigation of PTS Events for VVER NPPSof PTS Events for VVER NPPS

General DescriptionGeneral DescriptionTo meet current safety requirements for carrying out To meet current safety requirements for carrying out

WWER-1000 RPV WWER-1000 RPV vvisual surveyisual survey from outer surface from outer surface the the system SOKRAT was designed and manufactured based on system SOKRAT was designed and manufactured based on modern components and engineering solutionsmodern components and engineering solutions.

System "SOKRAT”: to perform visual survey System "SOKRAT”: to perform visual survey ffromrom the the outer surface of the cylindrical part of the VVER-1000/outer surface of the cylindrical part of the VVER-1000/V-320 RPV between weld joints Nos. 2 – 4 and bottom. V-320 RPV between weld joints Nos. 2 – 4 and bottom.

SSystem “SOKRAT” - up-to-date manipulator with elements ystem “SOKRAT” - up-to-date manipulator with elements of robotic-technology. of robotic-technology.

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

New System “SOKRAT” for WWER-1000 Reactor New System “SOKRAT” for WWER-1000 Reactor Pressure Vessel Visual Survey from Outer SurfacePressure Vessel Visual Survey from Outer Surface

General Description General Description (cont`d)(cont`d)

VVSS system “SOKRAT” consists of the following system “SOKRAT” consists of the following components:components:• mechanical equipment of manipulator;mechanical equipment of manipulator;• control equipment subsystem;control equipment subsystem;• coordinate subsystem with absolute and relative coordinate subsystem with absolute and relative

encoders;encoders;• laser positioning subsystem;laser positioning subsystem;• VT equipment subsystem. VT equipment subsystem.

Delivery of manipulator to working location beneath Delivery of manipulator to working location beneath RPV is performed with rail wheels.RPV is performed with rail wheels.

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

New System “SOKRAT” for WWER-1000 Reactor New System “SOKRAT” for WWER-1000 Reactor Pressure Vessel Visual Survey from Outer SurfacePressure Vessel Visual Survey from Outer Surface

The design of system “SOKRAT” is similar to system SKThe design of system “SOKRAT” is similar to system SK-187 -187 to some extentto some extent, , but but utilization of uputilization of up--toto--date light alloy materials allowed reducing a total weight fromdate light alloy materials allowed reducing a total weight from 5,7005,700kg kg ((SK-SK-187) 187) up to up to 400400kg kg (SOKRAT)(SOKRAT)..

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

Specific ComponentsSpecific Components

New System “SOKRAT” for WWER-1000 Reactor New System “SOKRAT” for WWER-1000 Reactor Pressure Vessel Visual Survey from Outer SurfacePressure Vessel Visual Survey from Outer Surface

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

Specific Components Specific Components (cont`d)(cont`d)

New System “SOKRAT” for WWER-1000 Reactor New System “SOKRAT” for WWER-1000 Reactor Pressure Vessel Visual Survey from Outer SurfacePressure Vessel Visual Survey from Outer Surface

Conclusions-3Conclusions-3The system “SOKRAT” for WWER-1000 RPV visual The system “SOKRAT” for WWER-1000 RPV visual

survey from outer surface is designed, developed and survey from outer surface is designed, developed and manufactured. manufactured.

Intensive factory acceptance testing and functional testing Intensive factory acceptance testing and functional testing showed:showed:• the system “SOKRAT” is very reliable and user friendly;the system “SOKRAT” is very reliable and user friendly;• can ensure essential reducing radiation doses of NPP can ensure essential reducing radiation doses of NPP

personnel;personnel;• system “SOKRAT” allows necessary values of positioning system “SOKRAT” allows necessary values of positioning

uncertainty and repeatability;uncertainty and repeatability;• UT system for WWER-1000 RPV can be developed at the UT system for WWER-1000 RPV can be developed at the

base of system “SOKRAT”.base of system “SOKRAT”.

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

New System “SOKRAT” for WWER-1000 Reactor New System “SOKRAT” for WWER-1000 Reactor Pressure Vessel Visual Survey from Outer SurfacePressure Vessel Visual Survey from Outer Surface

The result of the Ray casting algorithm using GPUThe result of the Ray casting algorithm using GPU

International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraineof the Taras Shevchenko National University of Kyivof the Taras Shevchenko National University of Kyiv

Library of the algorithms for medical images (tomography, Library of the algorithms for medical images (tomography, MRT), which is optimized for performance on the GPU using MRT), which is optimized for performance on the GPU using CUDA technologyCUDA technology

Development of Medical Image Processing Algorithms Optimized for Execution on GPUDevelopment of Medical Image Processing Algorithms Optimized for Execution on GPU

A full-featured implementation of the algorithm A full-featured implementation of the algorithm was created, based on histopiramid algorithm (similar to was created, based on histopiramid algorithm (similar to the octree) and parallel processing of the algorithm.the octree) and parallel processing of the algorithm.

Improvements were included: culling, clipping.Improvements were included: culling, clipping.The ability to work with 8 and 16-bit data was The ability to work with 8 and 16-bit data was

added.added.The control memory usage video card was realized.The control memory usage video card was realized.Optimization algorithm performance was made.Optimization algorithm performance was made.

Software Library of Marching Cubes AlgorithmSoftware Library of Marching Cubes Algorithm

Development of Medical Image Processing Algorithms Optimized for Execution on GPUDevelopment of Medical Image Processing Algorithms Optimized for Execution on GPU

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

The function of reducing the number of The function of reducing the number of triangles (mesh reduction) was realized.triangles (mesh reduction) was realized.

Optimization of the amount of memory used for Optimization of the amount of memory used for auxiliary arrays was made.auxiliary arrays was made.

Function of surface smoothing (mesh Function of surface smoothing (mesh smoothing) was realized. smoothing) was realized.

Software Library of Marching Cubes Algorithm Software Library of Marching Cubes Algorithm (cont`d)(cont`d)

Development of Medical Image Processing Algorithms Optimized for Execution on GPUDevelopment of Medical Image Processing Algorithms Optimized for Execution on GPU

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

Software Library of Marching Cubes Algorithm Software Library of Marching Cubes Algorithm (cont`d)(cont`d)

Result of algorithm Result of algorithm Marching Cubes Marching Cubes optimized for optimized for NVIDIA GPU NVIDIA GPU ((creation of medical volume surface with creation of medical volume surface with DICOM DICOM of files – tomography resultsof files – tomography results))

Development of Medical Image Processing Algorithms Optimized for Execution on GPUDevelopment of Medical Image Processing Algorithms Optimized for Execution on GPU

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

Library of the algorithms for medical images (tomography, Library of the algorithms for medical images (tomography, MRT), which is optimized for performance on the GPU using MRT), which is optimized for performance on the GPU using CUDA technologyCUDA technology

The result of the Marching Cubes algorithm using GPU (building The result of the Marching Cubes algorithm using GPU (building curved surface)curved surface)

Development of Medical Image Processing Algorithms Optimized for Execution on GPUDevelopment of Medical Image Processing Algorithms Optimized for Execution on GPU

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

For Ray casting algorithm performed on the GPU a speed For Ray casting algorithm performed on the GPU a speed enhancement was achieved in ~ 60 times compared to its enhancement was achieved in ~ 60 times compared to its implementation on the CPU. Time of construction of the image - implementation on the CPU. Time of construction of the image - <0.1 sec.<0.1 sec.

For Marching Cubes algorithm performed on the GPU a For Marching Cubes algorithm performed on the GPU a speed enhancement was achieved in ~ 40 times compared to its speed enhancement was achieved in ~ 40 times compared to its implementation on the CPU. Time of construction of the image - implementation on the CPU. Time of construction of the image - <0.5 sec.<0.5 sec.

The achieved speed enhancement of the algorithms allows The achieved speed enhancement of the algorithms allows to apply them for on-line analysis of the medical images (i.e. to apply them for on-line analysis of the medical images (i.e. doctor almost doesn't need to wait for rebuilding of the image doctor almost doesn't need to wait for rebuilding of the image while parameters are changing (angle of rotation, scale, etc.).while parameters are changing (angle of rotation, scale, etc.).

Conclusion-4Conclusion-4

Development of Medical Image Processing Algorithms Optimized for Execution on GPUDevelopment of Medical Image Processing Algorithms Optimized for Execution on GPU

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

Three-dimensional Polymer DosimetryThree-dimensional Polymer Dosimetry

3-D Dosimeters3-D Dosimeters3-D Dosimeters3-D Dosimeters

Polyurethane Polyurethane radiochromic radiochromic

dosimeterdosimeter

Fricke Fricke dosimeterdosimeter

Polymer Polymer gelsgels

Polymer gelsPolymer gels

The dose distribution in the The dose distribution in the polyurethane phantom polyurethane phantom

Ion Beam Cancer TherapyIon Beam Cancer Therapy Photon Cancer RadiotherapyPhoton Cancer Radiotherapy

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv Department of Nuclear Physics and EngineeringDepartment of Nuclear Physics and Engineering

Medical Physics Calculations for Ukrainian HospitalsMedical Physics Calculations for Ukrainian Hospitals

Shielding calculation for medical linear accelerators, Shielding calculation for medical linear accelerators, cyclotrons for PET technology, brachytherapy systems, cyclotrons for PET technology, brachytherapy systems, PET scanners and lab rooms.PET scanners and lab rooms.

Issues of radiation protection in the radiotherapy and PET Issues of radiation protection in the radiotherapy and PET divisions.divisions.

Special sewerage for PET department.Special sewerage for PET department. Argon-41 generation by medical cyclotrons (production of Argon-41 generation by medical cyclotrons (production of

F-18).F-18). Quality Assurance for radiotherapy (electron linear Quality Assurance for radiotherapy (electron linear

accelerators) and PET.accelerators) and PET. Activation of air and constructive materials in the vault of Activation of air and constructive materials in the vault of

medical liner accelerator.medical liner accelerator. Potential Contaminated Emissions due to PET Potential Contaminated Emissions due to PET

Technologies Operation.Technologies Operation.

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv Department of Nuclear Physics and EngineeringDepartment of Nuclear Physics and Engineering

Medical Physics Calculations for Central Ukrainian HospitalsMedical Physics Calculations for Central Ukrainian Hospitals

Shielding calculation for medical facilitiesShielding calculation for medical facilities

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv Department of Nuclear Physics and EngineeringDepartment of Nuclear Physics and Engineering

Medical Physics Calculations for Central Ukrainian HospitalsMedical Physics Calculations for Central Ukrainian Hospitals

Total activity of urine, removed in special sewerage during a day (linear and log scale).Total activity of urine, removed in special sewerage during a day (linear and log scale).

Special sewerage for PET departmentSpecial sewerage for PET department

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv Department of Nuclear Physics and EngineeringDepartment of Nuclear Physics and Engineering

Medical Physics Calculations for Central Ukrainian HospitalsMedical Physics Calculations for Central Ukrainian Hospitals

Activation of air and constructive materials in the vault Activation of air and constructive materials in the vault of medical liner acceleratorof medical liner accelerator

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv Department of Nuclear Physics and EngineeringDepartment of Nuclear Physics and Engineering

Medical Physics Calculations for Central Ukrainian HospitalsMedical Physics Calculations for Central Ukrainian Hospitals

Argon-41 generation by medical cyclotrons Argon-41 generation by medical cyclotrons (production of F-18)(production of F-18)

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv Department of Nuclear Physics and EngineeringDepartment of Nuclear Physics and Engineering

Medical Physics Calculations for Central Ukrainian HospitalsMedical Physics Calculations for Central Ukrainian Hospitals

Argon-41 generation by medical cyclotrons Argon-41 generation by medical cyclotrons (production of F-18)(production of F-18) ((cont`dcont`d))

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv Department of Nuclear Physics and EngineeringDepartment of Nuclear Physics and Engineering

Medical Physics Calculations for Central Ukrainian HospitalsMedical Physics Calculations for Central Ukrainian Hospitals

Potential Contaminated Emissions due to PET Potential Contaminated Emissions due to PET Technologies OperationTechnologies Operation

Harmful EffluentsHarmful Effluents

PET Technology stagesPET Technology stages Regular RiskRegular Risk Incident RiskIncident Risk Radioisotopes Radioisotopes

Cyclotron to producing PET isotope (F-18)Cyclotron to producing PET isotope (F-18) + gases & aerosols+ gases & aerosols F-18, Ar-41, N-13F-18, Ar-41, N-13

Synthesis of pharmaceuticals (FDG)Synthesis of pharmaceuticals (FDG) + gases & aerosols+ gases & aerosols F-18F-18

QAQA +?+? F-18F-18

Portioning and packagingPortioning and packaging +?+? F-18F-18

TransportationTransportation +?+? F-18F-18

Diagnostic proceduresDiagnostic procedures

– injection procedureinjection procedure +?+? F-18F-18

– uptake waiting period (after injection)uptake waiting period (after injection) + sewage+ sewage F-18F-18

– scanning proceduresscanning procedures ++ F-18F-18

– radiation safety waiting periodradiation safety waiting period (after (after scanning)scanning) + sewage+ sewage F-18F-18

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv Department of Nuclear Physics and EngineeringDepartment of Nuclear Physics and Engineering

We serve as technical team to assist designing medical We serve as technical team to assist designing medical facilities in Ukraine to meet national and international facilities in Ukraine to meet national and international requirements.requirements.

Operational support is provided with staff education and Operational support is provided with staff education and study of dangerous factors affecting patients and medical staff.study of dangerous factors affecting patients and medical staff.

Harmful effluents and radiation protection issues are Harmful effluents and radiation protection issues are studied to control and decrease releases into the environment.studied to control and decrease releases into the environment.

Conclusion-5Conclusion-5

Medical Physics Calculations for Central Ukrainian HospitalsMedical Physics Calculations for Central Ukrainian Hospitals

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv Department of Nuclear Physics and EngineeringDepartment of Nuclear Physics and Engineering

Our approach is based on many years experience and Our approach is based on many years experience and young vision.young vision.

Students are actively involved into solving new and Students are actively involved into solving new and difficult problems.difficult problems.

Multifunctional expertise is targeted to address complex Multifunctional expertise is targeted to address complex and interesting tasks.and interesting tasks.

We would be pleased to apply our skills for joint We would be pleased to apply our skills for joint projects and programs.projects and programs.

CONCLUSIONSCONCLUSIONS

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

Department of Nuclear Physics and EngineeringDepartment of Nuclear Physics and Engineering

Thank you for attention!Thank you for attention!

Taras Shevchenko National University of KyivTaras Shevchenko National University of Kyiv International Nuclear Safety Center of UkraineInternational Nuclear Safety Center of Ukraine

Department of Nuclear Physics and EngineeringDepartment of Nuclear Physics and Engineering