Assessment of dose during an SGTR

Conference · Thu Dec 31 23:00:00 EST 1992 · Transactions of the American Nuclear Society; (United States)

OSTI ID:6912370

Adams, J P ^[1]

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1. Idaho National Engineering Lab., Idaho Falls, ID (United States)

In pressurized water reactors (PWRs), water in the reactor coolant system (RCS) is pressurized to prevent it from boiling. This high-pressure water is circulated through heat exchanger tubes in steam generators where heat is transferred to the lower pressure secondary coolant system (SCS), producing steam that is used to generate electrical power. The tubes represent a large fraction of the RCS pressure boundary and rupture of these tubes [a steam generator tube rupture (SGTR)] can result in a direct release of radioactivity to the environment. The principal radiological concern during an SGTR results from the presence of radioactive iodine in the RCS coolant. This study assesses the overall effects of the results of analytical and experimental investigations on the calculated iodine dose to the environment during an SGTR.

• OSTI ID: 6912370
• Report Number(s): CONF-931160--
• Journal Information: Transactions of the American Nuclear Society; (United States), Journal Name: Transactions of the American Nuclear Society; (United States) Vol. 69; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

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