Results 91 to 100 of about 278 (148)

Analysis of embrittlement of WWER-1000 RPV materials

International Journal of Pressure Vessels and Piping, 2012
Abstract Analysis of embrittlement for WWER-1000 RPV materials is performed on the basis of available and original experimental data. Contributions of thermal aging and neutron irradiation to embrittlement are considered for base and weld metals. Equations have been obtained for the shift of the critical temperature of brittleness as a function of ...
B Z Margolin, D Yu Erak
exaly   +2 more sources

Evaluation of WWER-440 Surveillance at Paks NPS

1989
The surveillance program of the WWER-440 type pressurized water reactors (PWRs) is somewhat different from the surveillance programs of other PWRs. In view of this, a surveillance evaluation system was developed to solve the open questions connected with the design. This system was used to evaluate the results of the first two units of Paks NPS.
F Gillemot, P Trampus, J Rittinger
exaly   +2 more sources

WWER RPV embrittlement: start of life toughness

International Journal of Nuclear Knowledge Management, 2011
It is well known that neutron irradiation affects the properties of reactor pressure vessel material. The methodologies to assess the embrittlement of LWR (PWR, BWR and WWER types) are all based on the shift induced by irradiation of a reference transition temperature.
Marta Serrano, Jesus Lapena
exaly   +2 more sources

A historical review of WWER RPV embrittlement issues

International Journal of Nuclear Knowledge Management, 2011
The paper tries to describe the history of the radiation effects study in WWER type reactor pressure vessels – from their design, manufacturing and operation point of view. The paper shows the time evolution and also institutions that were and are included in this research and development study.
Milan Brumovsky
exaly   +2 more sources

The role of chemical composition in WWER RPV irradiation embrittlement

International Journal of Nuclear Knowledge Management, 2010
The main chemical elements influencing WWER RPV steel radiation embrittlement are copper, phosphorus, nickel and manganese. Copper and phosphorus are the main influencing elements for WWER-440 RPVs. The influence of copper is implemented in the forming of nanocluster centres rounded by other elements which are the effective barriers to dislocation ...
Luigi Debarberis
exaly   +2 more sources

Evolution of the structure of the WWER-1000 reactor vessel from the prototype model to WWER-1200

Strength of Materials, 2010
We discuss the guidelines used in the design of the vessels of WWER-1000 (water-cooled water-moderated) nuclear reactors. The characteristic specific features of the structure of the reactor vessel are discussed, and the subsequent steps of improvement of its design aimed at the increase in its operating safety and designed service life up to 60 years ...
V. I. Bakaldin, V. I. Kashirin, V. V. Petrov, V. G. Fedosov   +3 more
openaire   +1 more source

Destructive analysis of the nuclide composition of spent fuel of WWER-440, WWER-1000, and RBMK-1000 reactors

Radiochemistry, 2008
The results of analysis of spent nuclear fuel (SNF) by destructive methods, carried out systematically at the Khlopin Radium Institute for over 20 years till the mid-1990s, are presented. These data constitute the experimental base for the development of nondestructive methods, correction of calculation programs, substantiation of correlation ...
T. P. Makarova, B. A. Bibichev, V. D. Domkin   +2 more
openaire   +1 more source

Neutron Dosimetry Overview for WWERs

2018
Neutron dosimetry is a mandatory part of the monitoring of irradiation conditions within the reactor pressure vessels (RPVs) of all type of reactors, including water-water energetic reactors (WWERs). The main experimental part is connected with the surveillance specimen programs because the determination of neutron fluence in each of the surveillance ...
Milan Brumovský, Milan Marek
openaire   +1 more source

Assessment of the WWER-1000 reactor condition

International Journal of Pressure Vessels and Piping, 2006
The current state of the materials (steel, welds, anticorrosive cladding metal) of WWER-1000 RPVs has been examined, taking into consideration special features of their manufacture and operation for 30 years. The possibility of operating these reactors after their design service life has been estimated, allowing for the degradation of properties due to
B.T. Timofeev, G.P. Karzov
openaire   +1 more source