Deposition and control of /sup 7/Be in liquid lithium

Conference · Tue Jan 01 04:00:00 EST 1980

OSTI ID:5384169

Bechtold, R. A.

Preferential beryllium-7 deposition has been found in the higher temperature region of non-isothermal flowing lithium between 270/sup 0/C to 200/sup 0/C. Various methods for controlling /sup 7/Be distribution for application to the Fusion Materials Irradiation Test (FMIT) facility are examined. Flushing a loop with 425/sup 0/C lithium decreased /sup 7/Be activity on pipe walls by 60 to 80%. Yttrium has been found to be more effective than the other materials tested for removal of /sup 7/Be from lithium. Preliminary results on diffusion traps indicate effectiveness for /sup 7/Be removal also.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AC14-76FF02170
• OSTI ID: 5384169
• Report Number(s): HEDL-SA-1889-FP; CONF-800401-12
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ACCELERATORS
ALKALI METALS
ALKALINE EARTH ISOTOPES
BERYLLIUM 7
BERYLLIUM ISOTOPES
BETA DECAY RADIOISOTOPES
DAYS LIVING RADIOISOTOPES
DEPOSITION
ELECTRON CAPTURE RADIOISOTOPES
ELEMENTS
EVEN-ODD NUCLEI
FMIT LINAC
HIGH TEMPERATURE
ISOTOPES
LIGHT NUCLEI
LINEAR ACCELERATORS
LITHIUM
METALS
NUCLEI
RADIOACTIVITY
RADIOISOTOPES
REMOVAL
TRANSITION ELEMENTS
YTTRIUM