Results 211 to 220 of about 121,917 (257)

Development of Reconstitution Technology for Surveillance Specimens

10th International Conference on Nuclear Engineering, Volume 1, 2002
The Japan Power Engineering and Inspection Corporation (JAPEIC) has been carrying out the project titled “Nuclear Power Plant Integrated Management Technology (PLIM)” consigned by Japanese Ministry of Economy, Trade and Industry (METI) since 1996FY as a 10-years project. As one of the project themes, development of reconstitution technology for reactor
Yasushi Atago, Shunichi Hatano, Eiichiro Otsuka   +2 more
openaire   +1 more source

Surveillance Specimen Program for Lifetime Extension of RPV

18th International Conference on Nuclear Engineering: Volume 5, 2010
Plant life extension (as well as Long Term Operation) to 60 or 80 years of operation also requires a reliable information about the potential irradiation embrittlement (and also thermal ageing) of reactor pressure vessel materials. Such information is usually obtained from testing specimens within the surveillance specimen program that is designed for ...
Milan Brumovsky, Milos Kytka
openaire   +1 more source

Molecular Characterization of Vancomycin-Resistant Enterococci from Clinical and Surveillance Specimens

Infection Control & Hospital Epidemiology, 2006
Objective:To compare the molecular characteristics of infection-derived (ID) isolates and intestinal colonization–derived (ICD) isolates of vancomycin-resistant enterococci (VRE) recovered from hospitalized patients.Design.A 12-month prospective cohort study.Setting.A 1,000-bed teaching facility.Methods.From January through December 2004, a total of 30
Ji Young, Huh, Wee Gyo, Lee, Hye Young, Jin   +2 more
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Neutron fluence calculations for embrittlement surveillance specimens in VVER-1000

Annals of Nuclear Energy, 2009
Abstract Neutron fluence spectrum calculations have been performed for the reactor pressure vessel of a VVER-1000, applying the Monte Carlo code TRAMO. Activities measured earlier in Balakovo-1 by fluence monitors, placed in special Charpy surveillance containers, are compared to TRAMO results. The average deviation from the measurements is about 5%.
Konheiser, J., Mittag, S., Zaritsky, S.
openaire   +2 more sources

Modification of Pre-Cracked Charpy Specimens for Surveillance Specimen Programs

Volume 6: Materials and Fabrication, Parts A and B, 2009
Application of pre-cracked Charpy specimens with various depth of side-grooves is considered for fracture toughness prediction. Recommendations for prediction of temperature dependence of fracture toughness are given when using small-sized specimens with deep side-grooves.
Boris Margolin, Vladimir Nikolaev, Valentin Fomenko, Lev Ryadkov   +3 more
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Long Term Operation and Surveillance Specimen Program of WWER RPVs

ASME 2010 Pressure Vessels and Piping Conference: Volume 7, 2010
Long Term Operation (LTO) to 60 or 80 years of operation also requires a reliable information about the potential irradiation embrittlement (and also thermal ageing) of reactor pressure vessel materials. Such information is usually obtained from testing specimens within the surveillance specimen program that is designed for the design RPV life ...
Milan Brumovsky, Milos Kytka
openaire   +1 more source

Russian WWER Surveillance Specimen Programs

2018
This paper describes surveillance specimen programs of Water-Water Energetic Reactor (WWER) water-cooled water-moderated reactor pressure vessels and experiences of controlling the properties of first-generation WWER-440 reactor pressure vessels, which do not have surveillance specimens.
Anna Chernobaeva, Dmitry Erak, Vyacheslav Kochkin   +2 more
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Atom probe tomography of 15Kh2MFA Cr–Mo–V steel surveillance specimens

Micron, 2001
Abstract An atom probe study has been performed on 15Kh2MFA base and 10KhMFT weld metal surveillance specimens from a VVER-440/213C reactor to investigate the mechanisms that produce embrittlement in low copper materials during service. The composition of the base metal was Fe-0.06 at.% Cu, 3.1% Cr, 0.34% V, 0.46% Mn, 0.35% Mo, 0.07% Ni, 0.34% Si, 0 ...
M.K. Miller, K.F. Russell, J. Kocik, E. Keilova   +3 more
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IRRADIATION CONDITIONS FOR SURVEILLANCE SPECIMENS LOCATED INTO PLANE CONTAINERS INSTALLED IN THE WWER-1000 REACTOR OF UNIT 2 OF THE SOUTH-UKRAINIAN NPP

Reactor Dosimetry State of the Art 2008, 2009
O. V. GRYTSENKO, V. N. BUKANOV, S. M. PUGACH   +2 more
exaly   +2 more sources

Surveillance Specimen Programs for WWER Type Reactors

Volume 7: Operations, Applications, and Components, 2005
Reactor pressure vessels (RPV) are components with the highest importance for the reactor safety and operation as they contain practically whole inventory of fission material but they are damaged/aged during their operation by an intensive reactor radiation.
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