Betongs hållfasthet vid moderata temperaturbelastningar
(2013)Division of Structural Engineering
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:
http://lup.lub.lu.se/student-papers/record/4461103
- author
- Jönsson, Henrik and Tornberg, Robert
- supervisor
-
- Oskar Larsson LU
- Peter Lundqvist LU
- Mikael Oxfall LU
- organization
- year
- 2013
- 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}}, }