Radionuclide trap for liquid-metal-cooled reactors

Journal Article · Tue Apr 01 04:00:00 EST 1980 · Nucl. Technol.; (United States)

OSTI ID:7065564

McGuire, J C; Brehm, W F

Prototype radionuclide traps were tested in sodium loops containing irradiated sources (Source Term Control Loops 2 and 3) at 604 and 538/sup 0/C (1120 and 1000/sup 0/F). Prototype traps were 70 to 87% efficient in removing /sup 54/Mn from the sodium, and also effective for /sup 60/Co. Extensive screening tests showed that pure nickel is the most effective getter material, working best above 450/sup 0/C (842/sup 0/F) with increasing effectiveness at higher temperatures. Of the several possible trap sites considered for reactor use, a location within the top of the fuel assembly was chosen as the most convenient and effective. This position would facilitate trap handling by making trap insertion and removal an implicit part of the normal fuel handling procedure. A cost/benefit analysis shows that the radionuclide trap will be economically attractive.

• Research Organization: Hanford Engineering Development Lab., Richland, WA
• OSTI ID: 7065564
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 48:2; ISSN NUTYB
• Country of Publication: United States
• Language: English

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CORROSION PRODUCTS
EFFICIENCY
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FAST REACTORS
FBR TYPE REACTORS
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