Transport of beryllium-7 in a lithium loop

Journal Article · Sun Jul 01 04:00:00 EDT 1984 · Fusion Technol.; (United States)

OSTI ID:5595562

Katsuta, H; Anantatmula, R P; Bechtold, R A; Brehm, W F

A /sup 7/Be transport test was performed in the Beryllium-7 Experimental Lithium Loop with hot leg at 270/sup 0/C and cold leg at 230/sup 0/C. The ''cold leg'' test stringer was in a rising temperature region at 250/sup 0/C. A total of 108 test coupons were included in the material compatibility and deposition test programs, containing AISI Types 304 and 304L stainless steels, Fe-2 1/4 Cr1 MO, pure iron, molybdenum, beryllium, zirconium, titanium, yttrium, three different aluminide coatings on Type 304 stainless steel substrates, and both tubular and flat butt-welds of Type 304 stainless steel. An average lithium velocity of 1.36 m/s was established during the test which was terminated after 3718 h. The /sup 7/Be activity data indicated that the deposition of /sup 7/Be is a function of temperature. The cold leg positions displayed maximum /sup 7/Be deposition followed by the intermediate temperature locations (cold leg test stringer) and the hot leg locations. Two chemical forms of /sup 7/Be are expected in lithium, namely, unbonded /sup 7/Be at a low concentration, and a fine precipitate of /sup 7/Be/sub 3/N/sub 2/ at a high concentration. The deposit in the hot leg region is presumed to be primarily /sup 7/Be, while the cold leg deposit is mostly /sup 7/Be/sub 3/N/sub 2/. The cold leg specimens of a given material showed more /sup 7/Be deposition than the hot leg specimens of the same material, consistent with the /sup 7/Be activity data on the piping. Based on the present investigations and previous data, it is concluded that /sup 7/Be produced in the Fusion Materials Irradiation Test (FMIT) facility will have sufficient nitrogen in the lithium system to form /sup 7/Be/sub 3/N/sub 2/. It is expected that the majority of /sup 7/Be will be transported to the colder parts of the loop and deposited as /sup 7/Be/sub 3/N/sub 2/. However, a small amount of /sup 7/Be in the unbonded form will be in the hotter parts of the loop and is expected to diffuse into the steel piping.

• Research Organization: Japan Atomic Energy Research Institute, Naka-Muchi, Nika-gun, Ibaraki-Ken
• OSTI ID: 5595562
• Journal Information: Fusion Technol.; (United States), Journal Name: Fusion Technol.; (United States) Vol. 6:1; ISSN FUSTE
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700204* -- Fusion Power Plant Technology-- Cooling Systems
700206 -- Fusion Power Plant Technology-- Environmental Aspects
ACCELERATORS
ALKALI METALS
ALKALINE EARTH ISOTOPES
ALKALINE EARTH METAL COMPOUNDS
ALKALINE EARTH METALS
ALLOYS
ALUMINIUM COMPOUNDS
BERYLLIUM
BERYLLIUM 7
BERYLLIUM COMPOUNDS
BERYLLIUM ISOTOPES
BERYLLIUM NITRIDES
BETA DECAY RADIOISOTOPES
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-MOLYBDENUM STEELS
CHROMIUM-NICKEL STEELS
COATINGS
COMPATIBILITY
COOLING SYSTEMS
CORROSION RESISTANT ALLOYS
DAYS LIVING RADIOISOTOPES
DEPOSITION
ELECTRON CAPTURE RADIOISOTOPES
ELEMENTS
ENERGY SYSTEMS
EVEN-ODD NUCLEI
FMIT LINAC
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
JOINTS
LIGHT NUCLEI
LINEAR ACCELERATORS
LITHIUM
MATERIALS
MATERIALS TESTING
METALS
MOLYBDENUM
NICKEL ALLOYS
NITRIDES
NITROGEN COMPOUNDS
NUCLEI
PIPES
PNICTIDES
PROTECTIVE COATINGS
RADIOACTIVATION
RADIOACTIVITY TRANSPORT
RADIOISOTOPES
REMOVAL
STAINLESS STEEL-304
STAINLESS STEEL-304L
STAINLESS STEELS
STEELS
TEMPERATURE DEPENDENCE
TESTING
THERMONUCLEAR REACTOR COOLING SYSTEMS
THERMONUCLEAR REACTOR MATERIALS
TITANIUM
TRANSITION ELEMENTS
WELDED JOINTS
YTTRIUM
ZIRCONIUM