Transactions of the 8th International Conference on Structural Mechanics in Reactor Technology : Centre de conférences Albert Borschette, Brussels, Belgium, August 19-23, 1985 v. A

• Material Type: 図書
• ISBN: 0444869565; 0444869697
• Title: Transactions of the 8th International Conference on Structural Mechanics in Reactor Technology : Centre de conférences Albert Borschette, Brussels, Belgium, August 19-23, 1985
• Volume: v. A; set:
• Author/Editor: edited by Mme J. Stalpaert
• Author Heading: International Conference on Structural Mechanics in Reactor Technology; https://ci.nii.ac.jp/author/DA00922616
• Publication, Distribution, etc.: North-Holland
• Publication Date: c1985
• Publication Date (W3CDTF): 1985
• Size: 24 cm
• Place of Publication (Country Code): us
• Text Language Code: en
• Subject Heading: Nuclear power plants -- Design and construction -- Congresses; Structural engineering -- Research -- United States -- Congresses; Mechanical engineering -- United States -- Congresses
• Target Audience: 一般
• Note (General): Vol. A: Introduction, general contents, author index
• Related Material: LWR pressure components -- core structures, piping and vessels ; LWR pressure components -- effect of environment on materials and structures; https://cir.nii.ac.jp/crid/1130000796062375296; Thermomechanical analysis of fuel elements and asemblies ; Operating reactor structural experience; https://cir.nii.ac.jp/crid/1130000796227867392; Seismic response analysis of nuclear power plant systems; https://cir.nii.ac.jp/crid/1130000796683627008; Computer methods for structural analysis; https://cir.nii.ac.jp/crid/1130000797238242432; Concrete structures; https://cir.nii.ac.jp/crid/1130000797822135168; Extreme loading and response of reactor containments; https://cir.nii.ac.jp/crid/1130282268632839168; Inelastic behaviour of materials and constitutive equations; https://cir.nii.ac.jp/crid/1130282269030885248; Mechanical and thermal problems of fusion reactors; https://cir.nii.ac.jp/crid/1130282269272992896; Fracture mechanics and NDE; https://cir.nii.ac.jp/crid/1130282270147206912; Structural analysis of fast reactor core and coolant circuit structure; https://cir.nii.ac.jp/crid/1130282270797074432; Structural reliability ; Systems reliability of nuclear power plants; https://cir.nii.ac.jp/crid/1130282271858243072
• Related Material (URI): https://ci.nii.ac.jp/ncid/BA10990310#entity
• Data Provider (Database): 国立情報学研究所 : CiNii Research
• Original Data Provider (Database): CiNii Books; https://ci.nii.ac.jp/books
• NCID: https://ci.nii.ac.jp/ncid/BA10990310 : BA10990310

Table of Contents

LWR pressure components -- core structures, piping and vessels ; LWR pressure components -- effect of environment on materials and structures

Thermomechanical analysis of fuel elements and asemblies ; Operating reactor structural experience

Seismic response analysis of nuclear power plant systems

Computer methods for structural analysis

Concrete structures