Irradiation Effects on Reactor Structural Materials

Abstract

The report includes the following: (1) through-thickness radiation resistance of two A533 Grade B, Class I steel plates at 550 F, (2) directional notch ductility performance of irradiated 3-1/2Ni-Cr-Mo and 5Ni-Cr-Mo-V steel plates, (3) radiation sensitivity of A353 (9% nickel) steel as influenced by percent retained austenite, (4) tensile properties behavior versus postirradiation test temperature of selected structural steels, (5) potential for aging embrittlement of pressure vessel steels, (6) postpressurization test operations on PM-2A reactor pressure vessel, and (7) auxiliary equipment developed for elevated temperature remote tension testing of radioactive specimens.

Open PDF

Document Details

Document Type
Technical Report
Publication Date
Aug 15, 1967
Accession Number
AD0661229

Entities

People

  • Charles Z. Jr Serpan
  • E. P. Klier
  • Frank J. Loss
  • Henry E. Watson
  • J. Russell Hawthorne
  • Uldis Potapovs

Organizations

  • United States Naval Research Laboratory

Tags

Communities of Interest

  • Energy and Power Technologies
  • Ground and Sea Platforms

DTIC Thesaurus Topics

  • Ductile Brittle Transition
  • Ductility
  • Embrittlement
  • Fracture (Mechanics)
  • Heat Treatment
  • Impact Tests
  • Materials
  • Mechanical Working
  • Mechanics
  • Military Research
  • Nuclear Energy
  • Pressure Vessels
  • Reduction Of Area
  • Tensile Properties
  • Tensile Strength
  • Transition Temperature
  • Yield Strength

Readers

  • Metallurgy
  • Nuclear and Radiation Engineering.