Published 1976 | Version v1
Miscellaneous

Evaluation of A-1 reactor heavy-water calandria specimens

  • 1. Skoda, Plzen (Czechoslovakia). Zavod Vystavba Jadernych Elektraren
  • 2. Ustav Jaderneho Vyzkumu CSKAE, Rez (Czechoslovakia)

Description

Container chains with surveillance specimens were placed in two special channels of the core peripheral part to test changes in mechanical properties due to reactor operation of caisson tube material. The specimens were made from the caisson tube material and placed by eight pieces on the outer surface of the containers. The first removed specimens were tested for corrosion losses, tensile strength, and fractured surfaces were then assessed. The changes in strength properties were found to be similar in both base material and welded joints. The corrosion film on surveillance specimens did not practically affect strength properties nor ductility. It was found that the Al-Mg-Si alloy used for the heavy water vessel caisson tubes following stabilization annealing was fully stable at operating temperatures of up to 100 degC. Slio.ht changes in properties can be attributed to the effect of a high neutron dose. Thus, the high radiation and temperature stability of the alloy was confirmed. (O.K.)

Additional details

Additional titles

Original title (Czech)
Hodnoceni svedecnych vzorku trub tezkovodni nadoby reaktoru A-1

Publishing Information

Imprint Title
Radiation damage of nuclear reactor materials
Journal Page Range
p. 160-167.
Report number
INIS-mf--5272

Conference

Title
Symposium on radiation damage of nuclear reactor materials.
Dates
23 - 24 Nov 1976.
Place
Rez, Czechoslovakia.

Optional Information

Notes
Imprint:Radiacni poskozeni materialu jadernych reaktoru.