Published 1996 | Version v1
Miscellaneous

Radiation embrittlement of WWER-type reactor pressure vessel materials under reirradiation after annealing

  • 1. Pelotas Univ., RS (Brazil). Inst. de Quimica e Geociencias
  • 2. RRC Kurchatov Inst., Moscow (Russian Federation)
  • 3. Oak Ridge National Lab., TN (United States)
  • 4. Rio Grande do Sul Univ., Porto Alegre, RS (Brazil)

Description

Pressure vessel annealing is the unique method of irradiated reactor pressure vessel materials (RPVM) properties recovery. The present paper gives the results of investigation on recovery of the properties of the irradiated RPVM after annealing, repeated radiation (embrittlement) of RPVM during repeated irradiation (reirradiation) after annealing. The reembrittlement behaviour could be described by vertical, lateral and conservative shift of the initial transition temperature shift (TTS). The most restrictive conservative shift approach is used in the assessment of residual lifetime of annealed vessels. But experimental data and analysis shows that lateral shift approach could be representatively used to remove unnecessary conservatism. (author)

Availability note (English)

Available from the library of the Brazilian Nuclear Energy Commission, Rio de Janeiro

Additional details

Publishing Information

Imprint Pagination
5 p.

Conference

Title
6. General congress on nuclear energy
Original Conference Title
6. Congresso geral de energia nuclear
Dates
27 Oct - 1 Nov 1996
Place
Rio de Janeiro, RJ (Brazil)

Optional Information

Notes
7 refs., 8 figs.; vlevit@ufpel.tche.br; farhang@vortex.ufrgs.br