Tritium permeation and related studies on barrier treated 316 stainless steel

Conference · Sun Sep 01 00:00:00 EDT 1991

OSTI ID:10117750

Gilbert, E R; Allen, R P; Baldwin, D L; Bell, R D; Brimhall, J L; Clemmer, R G; Marschman, S C; McKinnon, M A; Page, R E; Powers, H G ^[1]; Chalk, S G ^[2]

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1. Pacific Northwest Lab., Richland, WA (United States)
2. USDOE, Washington, DC (United States)

To verify the performance of permeation-resistant cladding for tritium targets designed for a New Production Reactor Light Water Reactor, a tritium test facility was designed, developed, and certified. Testing is ongoing to verify the performance of reference designed targets. Accurate measurements were taken of tritium permeating from barrier-coated cladding specimens immersed in high-temperature autoclaves configured to simulate reactor coolant conditions. The tritium test pressure is controlled by heating a zirconium-alloy getter, previously charged with tritium, to a temperature that corresponds to a specified test pressure.

• Research Organization: Pacific Northwest Lab., Richland, WA (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 10117750
• Report Number(s): PNL-SA--19113; CONF-910920--35; ON: DE93005866
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220600
ALUMINATES
DIFFUSION
DIFFUSION BARRIERS
LITHIUM COMPOUNDS
NICKEL
PERMEABILITY
PRODUCTION REACTORS
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
SAFETY
STAINLESS STEEL-316
TARGETS
TESTING
TRITIUM