Probability of the iodine spike release rate during an SGTR (steam generator tube rupture)

Conference · Fri Jun 01 00:00:00 EDT 1990 · Transactions of the American Nuclear Society; (USA)

OSTI ID:6178987

Adams, J P; Atwood, C L ^[1]

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1. Idaho National Engineering Lab., Idaho Falls (USA)

The concern regarding the consequences of a steam generator tube rupture (SGTR) is dominated by the assumed presence of fission product iodine in the reactor coolant. These consequences (primarily radiation dose to the thyroid) vary considerably in magnitude, depending on several factors, including the concentration of fission product iodine in the reactor coolant. The standard review plant (SRP), used by utilities in producing a final safety analysis report, lists two categories of SGTRs: an SGTR that occurs sometime after initiation of an iodine spike and an SGTR that occurs coincident with an iodine spike. The SRP guidelines for an analysis of the second type specify that the initial reactor coolant system (RCS) concentration be assumed to be 1 {mu}Ci/g and that the iodine release rate (from the fuel to the coolant) be assumed to increase by a factor of 500 upon initiation of the transient. This paper addresses this SRP guideline (for the assumed iodine release rate during an SGTR with coincident iodine spike) by comparing it to measured iodine spiking that has occurred in operating pressurized water reactors (PWRs).

• OSTI ID: 6178987
• Report Number(s): CONF-900608--
• Journal Information: Transactions of the American Nuclear Society; (USA), Journal Name: Transactions of the American Nuclear Society; (USA) Vol. 61; ISSN TANSA; ISSN 0003-018X
• Country of Publication: United States
• Language: English

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