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Betongs hållfasthet vid moderata temperaturbelastningar

Jönsson, Henrik and Tornberg, Robert (2013)
Division of Structural Engingeering
Civil Engineering (M.Sc.Eng.)
Abstract
Reactor vessels in nuclear power plants are contained by a large prestressed concrete structure, which is subjected to elevated temperatures during operation. According to the American standard ACI 349, which is also used in Sweden, two limits should be carefully considered. These temperature limits are 66°C (150°F) and 93°C (200°F). Previous studies usually focus on concrete subjected to fire, thus the aforementioned moderate temperature loads are not widely studied in the aspect of strength in concrete.
The purpose of this master thesis is to gather information on the subject and perform tests on concrete which have been subjected to moderate elevated temperatures. A better understanding of how well the conditions of different reactor... (More)
Reactor vessels in nuclear power plants are contained by a large prestressed concrete structure, which is subjected to elevated temperatures during operation. According to the American standard ACI 349, which is also used in Sweden, two limits should be carefully considered. These temperature limits are 66°C (150°F) and 93°C (200°F). Previous studies usually focus on concrete subjected to fire, thus the aforementioned moderate temperature loads are not widely studied in the aspect of strength in concrete.
The purpose of this master thesis is to gather information on the subject and perform tests on concrete which have been subjected to moderate elevated temperatures. A better understanding of how well the conditions of different reactor vessels can be evaluated based on the gathered information. The main purpose is to investigate compressive and tensile strength but also changes in the modulus of elasticity and weight loss. (Less)
Please use this url to cite or link to this publication:
author
Jönsson, Henrik and Tornberg, Robert
supervisor
organization
year
type
H3 - Professional qualifications (4 Years - )
subject
report number
TVBK-5220
ISSN
0349-4969
language
Swedish
additional info
Examinator: Sven Thelandersson
id
4461103
date added to LUP
2014-06-12 15:32:33
date last changed
2014-06-12 15:32:33
@misc{4461103,
  abstract     = {Reactor vessels in nuclear power plants are contained by a large prestressed concrete structure, which is subjected to elevated temperatures during operation. According to the American standard ACI 349, which is also used in Sweden, two limits should be carefully considered. These temperature limits are 66°C (150°F) and 93°C (200°F). Previous studies usually focus on concrete subjected to fire, thus the aforementioned moderate temperature loads are not widely studied in the aspect of strength in concrete. 
The purpose of this master thesis is to gather information on the subject and perform tests on concrete which have been subjected to moderate elevated temperatures. A better understanding of how well the conditions of different reactor vessels can be evaluated based on the gathered information. The main purpose is to investigate compressive and tensile strength but also changes in the modulus of elasticity and weight loss.},
  author       = {Jönsson, Henrik and Tornberg, Robert},
  issn         = {0349-4969},
  language     = {swe},
  note         = {Student Paper},
  title        = {Betongs hållfasthet vid moderata temperaturbelastningar},
  year         = {2013},
}