Thermal hydraulic evaluation for an experimental facility to investigate pressurized thermal shock (PTS) in CDTN/CNEN
- 1. Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil)
Description
The goal of the work presented in this paper is to provide necessary thermal hydraulics information to the design of an experimental installation to investigate the Pressurized Thermal Shock (PTS) to be implemented at Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN). The envisaged installation has a test section that represents, in a small scale, a pressure vessel of a nuclear reactor. This test section will be heated and then exposed to a PTS in order to evaluate the appearance and development of cracks. To verify the behavior of the temperatures of the pressure vessel after a sudden flood through the annulus, calculations were made using the RELAP5/MOD 3.2.2 gamma code. Different outer radiuses were studied for the annular region. The results showed that the smaller annulus spacing (20 mm) anticipates the wetting of the surface and produces a higher cooling of the external surface, which stays completely wet for a longer time. (author)
Additional details
Additional titles
- Original title (Portuguese)
- Avaliacao termo-hidraulica da montagem experimental de choque termico pressurizado do CDTN/CNEN
Publishing Information
- Imprint Title
- Proceedings of the INAC 2002: International nuclear atlantic conference; 13. Brazilian national meeting on reactor physics and thermal hydraulics; 6. Brazilian national meeting on nuclear applications
- Imprint Pagination
- [3080 p.]
- Journal Page Range
- [6 p.]
Conference
- Title
- International nuclear atlantic conference; 13. Brazilian national meeting on reactor physics and thermal hydraulics; 6. Brazilian national meeting on nuclear applications
- Acronym
- INAC 2002
- Dates
- 11-16 Aug 2002
- Place
- Rio de Janeiro, RJ (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 33039536
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- COMPUTERIZED SIMULATION; CRACK PROPAGATION; EXPERIMENTAL DATA; HYDRAULICS; PRESSURE VESSELS; R CODES; TEMPERATURE DISTRIBUTION; THERMAL ANALYSIS; THERMAL SHOCK
- Descriptors DEC
- COMPUTER CODES; CONTAINERS; DATA; FLUID MECHANICS; INFORMATION; MECHANICS; NUMERICAL DATA; SIMULATION
Optional Information
- Notes
- 5 refs., 4 figs., 3 tabs., 10 graphs Imprint:Published only in CD-Rom