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Proceedings Papers

Properties of Cladding With Respect to RPV Integrity

Milan Brumovský
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A076, August 3, 2020
Paper No: PVP2020-21445
DOI: https://doi.org/10.1115/PVP2020-21445
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Topics: Cladding systems (Building), Vessels
Proceedings Papers

Evaluation of Reactor Internals Integrity and Lifetime According to the NTD ASI

Milan Brumovsky
Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A056, July 15–20, 2018
Paper No: PVP2018-84140
DOI: https://doi.org/10.1115/PVP2018-84140
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Topics: Control systems, Cracking (Materials), Creep, Design, Dimensions, Embrittlement, Failure, Ferrites (Magnetic materials), Fracture (Process), Fracture mechanics
Proceedings Papers

Interlaboratory Study for Small Punch Testing Preliminary Results

Milan Brumovsky, Radim Kopriva
Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A064, July 15–20, 2018
Paper No: PVP2018-84142
DOI: https://doi.org/10.1115/PVP2018-84142
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Topics: Testing, ASTM International, Damage, Power stations
Proceedings Papers

NTD ASI, Section IV: Evaluation of Residual Lifetime of Components and Piping in WWER Type NPPs

Milan Brumovsky
Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A050, July 15–20, 2018
Paper No: PVP2018-84139
DOI: https://doi.org/10.1115/PVP2018-84139
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Topics: Nuclear power stations, Pipes, Reactor vessels, Corrosion, Failure, Pressurized water reactors, Safety, Water, Damage, Design
Proceedings Papers

Age 60+ — Applicability of Ageing Related Data Bases and Methodologies for Ensuring Safe Operation of LWR Beyond 60 Years

Susan Ortner, Milan Brumovsky
Proc. ASME. PVP2017, Volume 6A: Materials and Fabrication, V06AT06A075, July 16–20, 2017
Paper No: PVP2017-65283
DOI: https://doi.org/10.1115/PVP2017-65283
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Topics: Databases, Light water reactors, Embrittlement, Alloy steel, Steel, Base metals, Collaboration, Concretes, Fluence (Radiation measurement), Fracture toughness
Proceedings Papers

Embrittlement Trend Curves for Notch and Fracture Toughness of 15Kh2MFAA Type Steel

Milan Brumovsky, Radim Kopřiva, Miloš Kytka
Proc. ASME. PVP2017, Volume 1A: Codes and Standards, V01AT01A063, July 16–20, 2017
Paper No: PVP2017-65174
DOI: https://doi.org/10.1115/PVP2017-65174
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Topics: Embrittlement, Fracture toughness, Steel, Surveillance, Reactor vessels, Databases, Fluence (Radiation measurement), Temperature effects, Vessels, Copper
eBook Chapter

Czech & Slovakian Codes

Publisher: ASME Press
Published: 2016
ISBN: 9780791861073
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Topics: Accidents, Chernobyl Nuclear Accident, Chornobyl, Ukraine, 1986, Design, Engineering standards, Governments, Nuclear power, Nuclear power stations
Proceedings Papers

Monitoring Degradation in Nuclear Reactors

Milan Brumovsky, Milos Kytka
Proc. ASME. PVP2015, Volume 7: Operations, Applications and Components, V007T07A004, July 19–23, 2015
Paper No: PVP2015-45511
DOI: https://doi.org/10.1115/PVP2015-45511
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Topics: Cutting, Damage, Design, Eddies (Fluid dynamics), Eddy currents (Electricity), In-service inspection, Nondestructive evaluation, Nuclear reactions, Nuclear reactor materials, Nuclear reactors
Proceedings Papers

Austenitic Cladding and Master Curve

Milan Brumovsky, Milos Kytka, Radim Kopriva, Michal Falcnik
Proc. ASME. PVP2015, Volume 1B: Codes and Standards, V01BT01A026, July 19–23, 2015
Paper No: PVP2015-45502
DOI: https://doi.org/10.1115/PVP2015-45502
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Topics: Cladding systems (Building), Fracture toughness, Temperature, Welding, Boiling water reactors, Ethers (Class of compounds), Ferrites (Magnetic materials), Irradiation (Radiation exposure), Phase transition temperature, Pressurized water reactors
Proceedings Papers

Comparison of Transition Temperature Shifts From Notch Impact and Fracture Toughness (Master Curve) Testing

Milan Brumovsky, Milos Kytka, Michal Falcnik
Proc. ASME. PVP2015, Volume 1B: Codes and Standards, V01BT01A023, July 19–23, 2015
Paper No: PVP2015-45154
DOI: https://doi.org/10.1115/PVP2015-45154
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Topics: Fracture toughness, Phase transition temperature, Testing, Irradiation (Radiation exposure), Impact testing, Surveillance, Temperature, Design, Embrittlement, Fluence (Radiation measurement)
Proceedings Papers

Correlation Between Transition Temperature Shifts of Impact Tests Using Standard and Subsize Specimens

Milan Brumovsky, Milos Kytka
Proc. ASME. PVP2015, Volume 1A: Codes and Standards, V01AT01A057, July 19–23, 2015
Paper No: PVP2015-45153
DOI: https://doi.org/10.1115/PVP2015-45153
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Topics: Impact testing, Phase transition temperature, Ductile fracture, Steel
Proceedings Papers

Role of Irradiation Embrittlement in RPV Lifetime Assessment

Milan Brumovský, Miloš Kytka
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T02A013, July 29–August 2, 2013
Paper No: ICONE21-15420
DOI: https://doi.org/10.1115/ICONE21-15420
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Topics: Embrittlement, Irradiation (Radiation exposure), Design, Radiation damage, Engineering standards, Failure, Fluence (Radiation measurement), Fracture mechanics, Hardening, Neutron flux
Proceedings Papers

Comparison of PTS Guides for Reactor Pressure Vessel Integrity Assessment

Milan Brumovsky
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T07A007, July 29–August 2, 2013
Paper No: ICONE21-15419
DOI: https://doi.org/10.1115/ICONE21-15419
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Topics: Reactor vessels, Fracture mechanics, ASME Standards, Cooling, Emergencies, Materials degradation, Materials properties, Nuclear power stations, Safety, Testing
Proceedings Papers

Comparison of PTS Guides for Reactor Pressure Vessel Integrity Assessment

Milan Brumovsky
Proc. ASME. PVP2013, Volume 3: Design and Analysis, V003T03A059, July 14–18, 2013
Paper No: PVP2013-97342
DOI: https://doi.org/10.1115/PVP2013-97342
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Topics: Reactor vessels, Fracture mechanics, ASME Standards, Cooling, Emergencies, Materials degradation, Materials properties, Nuclear power stations, Safety, Testing
Proceedings Papers

VERLIFE - Unified Procedure for Lifetime Assessment of Components and Piping in WWER NPPs During Operation: Updating and Further Development

Milan Brumovsky
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 463-467, May 17–21, 2010
Paper No: ICONE18-30256
DOI: https://doi.org/10.1115/ICONE18-30256
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Topics: Nuclear power stations, Pipes, Corrosion, Damage, Design, Erosion, Fracture mechanics, In-service inspection, Leak-before-break, Manufacturing
Proceedings Papers

Surveillance Specimen Program for Lifetime Extension of RPV

Milan Brumovsky, Milos Kytka
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 369-374, May 17–21, 2010
Paper No: ICONE18-30258
DOI: https://doi.org/10.1115/ICONE18-30258
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Topics: Surveillance, Design, Life extension, Nuclear power stations, Reactor vessels, Embrittlement, Irradiation (Radiation exposure), Temperature, Testing
Proceedings Papers

Microstructural Changes Related to Through-Wall Attenuation of Neutron Irradiation Embrittlement

Naoki Soneda, Kenji Nishida, Kenji Dohi, Akiyoshi Nomoto, William L. Server, Milan Brumovsky, Milos Kytka, Jack Spanner
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 119-124, July 18–22, 2010
Paper No: PVP2010-25636
DOI: https://doi.org/10.1115/PVP2010-25636
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Topics: Embrittlement, Irradiation (Radiation exposure), Neutrons, Copper, Mechanical properties, Atoms, Fluence (Radiation measurement), Steel, Fracture toughness, Metals
Proceedings Papers

Long Term Operation and Surveillance Specimen Program of WWER RPVs

Milan Brumovsky, Milos Kytka
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 7, 203-209, July 18–22, 2010
Paper No: PVP2010-25620
DOI: https://doi.org/10.1115/PVP2010-25620
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Topics: Surveillance, Design, Embrittlement, Irradiation (Radiation exposure), Life extension, Nuclear power stations, Reactor vessels, Temperature, Testing
Proceedings Papers

VERLIFE: Unified Procedure for Lifetime Assessment of Components and Piping in WWER NPPs During Operation—Updating and Further Development

Milan Brumovsky
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 1, 791-795, July 18–22, 2010
Paper No: PVP2010-25624
DOI: https://doi.org/10.1115/PVP2010-25624
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Topics: Nuclear power stations, Pipes, Reactor vessels, Corrosion, Damage, Design, Erosion, Failure, Fracture mechanics, Leak-before-break
Proceedings Papers

IAEA Coordinated Research Project on Master Curve Approach to Monitor Fracture Toughness of RPV Steels: Final Results of the Experimental Exercise to Support Constraint Effects

Randy K. Nanstad, Milan Brumovsky, Rogelio Herna´ndez Callejas, Ferenc Gillemot, Mikhail Korshunov, Bong Sang Lee, Enrico Lucon, Marc Scibetta, Philip Minnebo, Karl-Fredrik Nilsson, Naoki Miura, Kunio Onizawa, Tapio Planman, William Server, Brian Burgos, Marta Serrano, Hans-Werner Viehrig
Proc. ASME. PVP2009, Volume 3: Design and Analysis, 573-585, July 26–30, 2009
Paper No: PVP2009-78022
DOI: https://doi.org/10.1115/PVP2009-78022
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Topics: Fracture toughness, Steel, Carbon reinforced plastics, Temperature, Resolution (Optics), Surveillance, ASTM International, Finite element analysis, Geometry, Modeling