Effects of neutron dose, dose rate, and irradiation temperature on the irradiation embrittlement of a low-copper reactor pressure vessel steel

Ryuta Kasada, Takeshi Kudo, Akihiko Kimura, Hideki Matsui, Minoru Narui

Research output: Contribution to journalArticlepeer-review

5 Citations (Scopus)

Abstract

A series of irradiation experiments to investigate the effects of neutron fluence and flux on reactor pressure vessel (RPV) steels has been performed using the Japan Material Testing Reactor (JMTR). The irradiation temperature has been precisely controlled at 290°C within an error of ±2° during reactor operation. The neutron fluence and flux ranged from 9.3 × 1017 to 1.1 × 1020 n/cm2 and from 1.4 × 1011 to 6.3 × 1013 n/cm2/s, respectively. The material used in the present study was an A533B RPV steel in which the copper and phosphorous concentrations are 0.03 and 0.002 wt%, respectively. Charpy impact test results with one-third sized specimens showed no dose-rate dependence. Microstructural observation revealed that a higher irradiation temperature at around 340°C resulted in formation of rather large dislocation loops and smaller microvoids.

Original languageEnglish
Pages (from-to)213-223
Number of pages11
JournalJournal of ASTM International
Volume2
Issue number3
Publication statusPublished - 2005 Mar 1
Externally publishedYes

Keywords

  • Charpy impact test
  • Dose rate effects
  • Irradiation embrittlement
  • Irradiation hardening
  • Reactor pressure vessel steel

ASJC Scopus subject areas

  • Environmental Engineering
  • Materials Science(all)
  • Nuclear Energy and Engineering
  • Engineering(all)
  • Public Health, Environmental and Occupational Health

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