Results 211 to 220 of about 12,613 (263)

PRESSURE VESSEL CALCULATIONS FOR VVER-440 REACTORS

Reactor Dosimetry in the 21st Century, 2003
For the determination of the fast neutron load of the reactor pressure vessel a mixed calculational procedure was developed. The procedure was applied to the Unit II of Paks NPP, Hungary. The neutron source on the outer surfaces of the reactor was determined by a core design code, and the neutron transport calculations outside the core were performed ...
G, Hordósy, Gy, Hegyi, A, Keresztúri, Cs, Maráczy, E, Temesvári, P, Vértes, E, Zsolnay   +6 more
openaire   +2 more sources

Control system for reactor vessel inspection manipulator

2009 IEEE Control Applications, (CCA) & Intelligent Control, (ISIC), 2009
In this paper a system for control and 3D visualization of a manipulator for weld inspection of nuclear reactor vessels is described. Based on a client-server TCP/IP software architecture, the presented control system enables an operator to perform the entire inspection procedure remotely over a network, avoiding exposure to dangerous radiation which ...
Alan Mutka, Ivica Draganjac, Zdenko Kovacic, Zeljko Postruzin, Ranko Munk   +4 more
openaire   +2 more sources

Aseismic study on the reactor vessel of a fast breeder reactor

Nuclear Engineering and Design, 1984
Abstract This paper presents the results of a seismic study using an 1 8 th scale steel model and a 1 4 th scale plastic model which simulate the reactor vessel of a loop type Fast Breeder Reactor (FBR). The main purposes of this study are to confirm the structure/liquid interaction and the aseismic safety of the reactor vessel ...
K. Fujita, T. Ito, T. Matsuo, T. Shimomura, M. Morishita   +4 more
openaire   +1 more source

Problems in the design and construction of large reactor vessels☆

Nuclear Engineering and Design, 1965
Abstract The new “ASME boiler and pressure vessel code for nuclear vessels” permits design of nuclear reactor vessels for water reactor plants of up to 1500 MW. The problems of design, material procurement, and inspection are surveyed.
A.L. Gaines, L. Porse
openaire   +1 more source

French Reactor Vessel Integrity

Volume 7: Operations, Applications and Components, 2012
The French fleet comprises 58 PWR. The integrity of the reactor pressure vessel is one of the main considerations regarding plant life extension. The limiting damage is the irradiation embrittlement associated with brittle fracture risk.
openaire   +1 more source

Development of an underwater robot for nuclear reactor vessel

2013 IEEE International Conference on Robotics and Biomimetics (ROBIO), 2013
In this paper, an underwater robot for inspecting and maintaining nuclear reactor vessel is developed. Based on the kinematics analysis of the robot, the workspace is obtained. In order to evaluate the influence of water environment to the robot, the hydrodynamic forces including water resistance and additional mass force are analyzed.
Xiaojun Zhang, Jianhua Zhang, Jie Yuan, Manhong Li   +3 more
openaire   +1 more source

Structural integrity assessment of the reactor pressure vessel under the external reactor vessel cooling condition

Nuclear Engineering and Design, 1999
Since the suggestion of external reactor vessel cooling (ERVC), the effects of melting and cooling on the response of structural integrity of the reactor pressure vessel (RPV) under core melting accident conditions have been investigated. To investigate the initial behavior of RPV lower head and the effects of analysis conditions on the structural ...
Jong Sung Kim, Tae Eun Jin
openaire   +1 more source

Evaluation of in-vessel corium retention through external reactor vessel cooling for small integral reactor

Nuclear Engineering and Design, 2013
Abstract A criterion to prevent reactor vessel failure using in-vessel corium retention through the external reactor vessel cooling (IVR-ERVC) of a small integral reactor has been evaluated during a severe accident. A thermal load analysis from the corium pool to the outer reactor vessel wall in the lower plenum of the reactor vessel was performed to
Rae-Joon Park, Jae Ryong Lee, Kwang Soon Ha, Hwan Yeol Kim   +3 more
openaire   +1 more source

The MONOLITH Container: A New Development for Transportation and Storage of Reactor Vessel Equipment and Reactor Vessel Parts

Volume 2: Mgmt. Low/Interm. Level Waste; Spent Fuel; Economics/Analyses for Waste Mgmt.; Radiological Characterization/Application Release Criteria; Panel Sessions; Solid Waste Reduction/Treatment; Current Activities in Central/Eastern Europe; Environmental Remediation Technology; LL/ILW; HLW/Spent Fuel; Chernobyl; D&D Waste; Performance Assessment; MOX and Spent UOX; D&D Nuclear Reactors; Decommissioning of Other Nuclear Facilities, 2001
Abstract The cast iron container MONOLITH is a shielding container corresponding to the Konrad VI container with a max weight of 20 t. As cask content only dry activated and contaminated metallic material is allowed. After loading with this radioactive material the empty spaces inside the container are filled with other contaminated ...
H. Kalwa, G. Gestermann, D. Brüning
openaire   +1 more source

CHF enhancement by vessel coating for external reactor vessel cooling

Nuclear Engineering and Design, 2006
Abstract In-vessel retention (IVR) is a key severe accident management (SAM) strategy that has been adopted by some operating nuclear power plants and proposed for some advanced light water reactors (ALWRs). One viable means for IVR is the method of external reactor vessel cooling (ERVC) by flooding the reactor cavity during a severe accident.
J. Yang, M.B. Dizon, F.B. Cheung, J.L. Rempe, K.Y. Suh, S.B. Kim   +5 more
openaire   +1 more source