Results 111 to 120 of about 935 (164)

Dismantling Techniques for Reactor Steel Structures

Nuclear Technology, 1989
Two techniques have been developed for the underwater dismantlement of the steel components of the Japan Power Demonstration Reactor (JPDR): the plasma arc for dismantling the reactor internals and...
Satoshi Yanagihara, Yoshihiro Seiki, Hisashi Nakamura   +2 more
openaire   +1 more source

Neutronography of Irradiated Reactor Austenitic Steels

Crystallography Reports, 2021
The neutron diffracttion studies of the samples of fuel element claddings made of EK-164 and ChS-600 austenitic steels in the initial state and after operation in a BN-600 fast neutron reactor are reviewed. The samples were investigated in a wide range of fast neutron doses and irradiation temperatures, up to ∼80 displacements per atoms (dpa) and 628°C,
openaire   +1 more source

The economical use of steel in reactors

Journal of Nuclear Energy. Part A. Reactor Science, 1960
Abstract The fundamentals of the economical use of steel in reactor construction are discussed. It is shown that in stationary reactors the main way of economizing is to replace steel by concrete. Data are given which indicate that the mechanical strength and radiation resistance of modern concretes are by no means fully utilized, and that fine ...
openaire   +1 more source

Hydrogen permeability of reactor steels

Materials Science, 2011
The hydrogen permeability of 12Kh18N10T, 316SS, and 10Kh9VFA reactor steels and EP-838 and Kh12G20V alloyed chrome-manganese steels is studied in the intact state, after thermal treatment, alloying, application of protective coatings, oxidation, irradiation with H+ ions, and in the presence of welded joints. We compute the permeation of hydrogen P
openaire   +1 more source

Stainless steel reactor pressure vessels

Nuclear Engineering and Design, 1970
Abstract The properties of stainless steels preferred for nuclear reactor pressure vessel construction, the austenitic-chromium-nickel types, are reviewed along with other bases for this nuclear application. The engineering criteria which establish the limits for design and operation, the various aspects of vessel fabrication and the implications of ...
P.J. Karnoski, W.J. Fretague, Uldis Potapovs, L.E. Steele   +3 more
openaire   +1 more source

Induction Annealing of Austenitic Spring Steels for Nuclear Reactors

Journal of Nuclear Engineering and Radiation Science, 2020
Abstract This paper describes designing and experimental trials of an induction annealing method for AISI 321H austenitic steel wires. Specifically, it explores the feasibility of incorporating an existing frequency controller into a wire drawing line to provide induction heating of the wire stock to annealing temperatures.
Hájek, Jiří, Rot, David, Čubrová, Jana, Jiřinec, Jakub   +3 more
openaire   +3 more sources

Dismantling Techniques for Reactor Steel Piping

Nuclear Technology, 1989
Two cutting techniques have been developed for dismantling the pipes connected to the Japan Power Demonstration Reactor (JPDR) pressure vessel. They are the rotary disk knife cutting system for dismantling relatively large pipes, such as the primary cooling system, and the shaped explosive cutting systems for cutting relatively small pipes in air or ...
Satoshi Yanagihara, Fujio Hiraga, Hisashi Nakamura   +2 more
openaire   +1 more source

Ways of saving steel in reactor construction

The Soviet Journal of Atomic Energy, 1961
The basic methods for saving steel in reactor construction are considered in this article. It is shown that, in stationary nuclear reactors, the basic method for saving steel is its replacement with concrete. The article provides data indicating that the mechanical strength and the radiation resistance of concretes are not being utilized to the fullest
openaire   +1 more source

Comparison of austenitic stainless steels and martensitic steels for fusion reactors

Plasma Devices and Operations, 1996
Abstract This paper compares design related properties of austenitic stainless and martensitic steels as reauired for a fusion device and raakes an assessment of the R & D programs needed to address their critical issues. More precisely, the paper compares the properties of the Type 316LN steel and the modified 9Cr-1Mo steel, both of which are code ...
openaire   +1 more source

Synchrotron radiation‐induced TXRF of reactor steel samples

X‐Ray Spectrometry, 2001
Abstract Synchrotron radiation‐induced total reflection x‐ray fluorescence (TXRF) analysis was used for the trace element analysis of steels exploited in the construction of core components of existing fission plants and future fusion power plants.
Pepponi, Giancarlo, Peter Wobrauschek, Christina Streli, N. Zoger, Ferenc Hegedus   +4 more
openaire   +2 more sources