Postulated long-term loss of coolant accidents (LOCA) for the International Thermonuclear Experimental Reactor (ITER) may involve the ingress of air or steam into the plasma chamber. Reactions of these gases with the hot plasma facing components will cause oxidation, transport, and release of activated species. To predict radioactivity releases, we measured volatility rates from a tungsten alloy. Tests were performed in air or steam between 600 and 1200°C for 1 to 20 h. We used these volatilization rates to calculate radioactivity releases from severe hypothetical ITER accidents. We found that both the first wall and divertor plates fabricated from or coated with tungsten may release significant radioactivity in severe hypothetical LOCAs. Without radioactivity confinement or credit for in-plant deposition, the site boundary Early Effective Dose Equivalent (EDE) acceptance criterion of 100 mSv (10 rem) is exceeded by a factor of about thirty in either an air or steam accident. With radioactivity confinement and reference LOCA conditions of 700°C for the divertor plates and 600°C for the first wall, air and steam provide doses of 50 and 30 mSv, respectively. We conclude that tungsten-bearing components are not attractive from a passive safety standpoint. With radioactivity confinement and reference conditions, however, these components can meet the anticipated regulatory criterion.