Release of 14C from the gap and grain-boundary regions of used candu fuels to aqueous solutions

Author:

Stroes-Gascoyne S.,Tait J.C.,Porth R.J.,McConnell J.L.,Lincoln W.J.

Publisher

Elsevier BV

Subject

Waste Management and Disposal

Reference24 articles.

1. Nuclear fuel waste disposal in Canada—the generic research program;Dormuth,1990

2. The relationship between gap inventories of stable Xe, 137Cs and 129I used CANDU fuel;Stroes-Gascoyne;Nucl. Technol.,1987

3. Leaching of whole, defected used CANDU™ fuel elements in saline solutions under argon pressure;Stroes-Gascoyne,1989

4. Instant release of 14C, 99Tc, 90Sr and 137Cs from used CANDU fuel at 25°C in distilled deionized water;Stroes-Gascoyne,1992

5. Measurements of grain-boundary inventories of 137Cs, 90Sr and 99Tc in used CANDU fuel;Stroes-Gascoyne,1993

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