Note on stress analysis of prestressed concrete reactor pressure vessels-Reference-Cited by-同舟云学术

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Note on stress analysis of prestressed concrete reactor pressure vessels

Published:1965-01 Issue:1 Volume:1 Page:133-136
ISSN:0369-5816
Container-title:Nuclear Structural Engineering
language:en
Short-container-title:Nuclear Structural Engineering

Author:

Jaeger T.A.

Publisher

Elsevier BV

Subject

General Medicine

Reference33 articles.

1. Stresses in Hollow Cylinders Due to Asymmetrical Heat Generation

2. Temperature and thermal stress distributions in concrete primary shields for nuclear reactors;Thomas,1962

3. STRZ — a 7090 FORTRAN program for the steady-state temperature distribution in r–z geometry with temperature and direction dependent heat conduction coefficients and radiation in narrow gaps;Boonstra;Reactor Centrum Nederland, RCN-16,1963

4. Theory of elasticity;Timoshenko,1951

Cited by 4 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Concrete Reactor Pressure Vessels;Structures for Nuclear Facilities;2010-08-24

2. Reactor pressure vessel design and practice;Progress in Nuclear Energy;1982-01

3. Structural characteristics of cylindrical pressure vessels of medium thickness;Nuclear Engineering and Design;1966-08

4. Method for thermoviscoelastic stress analysis in concrete reactor vessels;Nuclear Structural Engineering;1965-04

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