International Concrete Abstracts Portal

Showing 1-5 of 2486 Abstracts search results

Document: 

CI4704NexInsights

Date: 

April 1, 2025

Publication:

Concrete International

Volume:

47

Issue:

4

Abstract:

There is a lack of comprehensive guidelines for the use of fiber-reinforced polymer (FRP) dowels in concrete pavement construction. In light of this, NEx: An ACI Center of Excellence for Nonmetallic Building Materials has announced a newly published document SG23.03 (25): NEx Guideline: FRP Dowels in Concrete Pavements.


Document: 

CI4704NEUnews

Date: 

April 1, 2025

Publication:

Concrete International

Volume:

47

Issue:

4

Abstract:

NEU: An ACI Center of Excellence for Carbon Neutral Concrete remains dedicated to supporting the built environment by maximizing resource efficiency and promoting the adoption of cutting-edge materials and intelligent engineering solutions. NEU amplifies efforts to disseminate knowledge on lowering the carbon footprint of concrete construction and advancing next-generation technologies.


Document: 

CI4703BuildingtheFuture

Date: 

March 1, 2025

Publication:

Concrete International

Volume:

47

Issue:

3

Abstract:

Hosted by the Concrete Innovation Council (CIC), the session “Innovations in Concrete” will be held on March 30, 2025, at the ACI Concrete Convention – Spring 2025 in Toronto, ON, Canada. The theme is “Implementing Low Carbon Concrete – From Innovation to Reality.” Later this year, the ACI Foundation 2025 Concrete Innovation Forum will be held August 12-14, 2025, at the Hotel Clio, Denver, CO, USA. The focus will be on how new practices, materials, or inventions move from the lab to the field.


Document: 

CI4701Wilson

Date: 

January 1, 2025

Author(s):

Michelle L. Wilson

Publication:

Concrete International

Volume:

47

Issue:

1

Abstract:

The concrete industry is at a turning point, with a growing focus on sustainability reshaping how cement and concrete are designed, produced, and implemented. To remain relevant in today’s market, all industry stakeholders must stay informed about evolving practices and new materials that can support sustainable construction.


Document: 

SP364_3

Date: 

December 1, 2024

Author(s):

Minkyu Kim, Tae-Hyun Kwon, Gyeonghee An, and Habeun Choi

Publication:

Symposium Papers

Volume:

364

Abstract:

The containment structure of a nuclear power plant is the last barrier of defense to maintain safety in the event of a severe accident, and the integrity of the containment building is the last line of defense against the release of radioactive material. Nuclear power plant containment buildings are most commonly constructed of prestressed concrete, but there are also some constructed of steel. In the case of PS concrete containment building, in order to prepare for the increase in internal pressure in the event of a severe accident, compression force is applied using a tendon in advance to secure sufficient safety, but due to the characteristics of concrete, cracks may occur, and these cracks may become a pathway for external leakage of radioactive materials in the event of a severe accident. In addition, a number of corroded cavities and degradation of liner plates have been found in recent Korean nuclear power plants. Therefore, a study to evaluate the safety of PS concrete containment buildings began in 2022, started by the Korea Atomic Energy Research Institute, and will be conducted for eight years until 2029. The purpose of the research can be categorized into two main areas. The first is to derive the probability of failure of concrete containment buildings due to an increase in internal pressure in the event of a severe accident. The second objective is to estimate the amount of radioactive material leakage through cracks in the containment building when cracks occur. The current methods for calculating the amount of leakage are approximate and based on many assumptions, and therefore contain too much uncertainty. The results of this study will be used to determine the probability of damage to the containment building in the event of a severe accident at a nuclear power plant, and to quantitatively evaluate the amount of radioactive material leakage to the outside, thereby quantitatively evaluating the amount of external exposure. This paper describes progress to date and potential outcomes rather than highly technical results.

DOI:

10.14359/51745455


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