Analytical determination of SCS pH during an SGTR

Conference · Tue Dec 31 23:00:00 EST 1991 · Transactions of the American Nuclear Society; (United States)

OSTI ID:7044004

Adams, J P; Peterson, E S ^[1]

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

The purpose of the study documented by this paper was to analytically assess the expected steam generator secondary pH during a steam generator tube rupture (SGTR). The principal radiological concern during an SGTR results from the presence of radioactive iodine, which has been transported from the reactor coolant system (RCS) to the secondary coolant system (SCS), and from the degree of volatility of this iodine. This study was initiated because of the correlation of iodine volatility and SCS pH.

• OSTI ID: 7044004
• Report Number(s): CONF-920606--
• Journal Information: Transactions of the American Nuclear Society; (United States), Journal Name: Transactions of the American Nuclear Society; (United States) Vol. 65; ISSN TANSA; ISSN 0003-018X
• Country of Publication: United States
• Language: English

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