Posttest data analysis of FIST experimental TRAC-BD1/MOD1 power transient experiment

Conference · Sun Jan 01 00:00:00 EST 1984

OSTI ID:6315015

Wheatley, P D; Wagner, K C

The FIST power transient test 6PMC2 was analyzed to further the understanding of the FIST facility and provide an assessment of TRAC-BD1/MOD1. FIST power transient 6PMC2 investigated the thermal-hydraulic response following inadvertent closure of the main steam isolation valve and the subsequent failure of the reactor to scram. Failure of the high pressure core spray system was also assumed, resulting in only the reactor core isolation cooling flow for inventory makeup during the transient. The experiment was a sensitivity study with relatively high core power and low makeup rates. This study provides one of the first opportunities to assess TRAC-BD1/MOD1 under power transient and natural circulation conditions with data from a facility with prototypical BWR geometry. The power transient test was analyzed with emphasis on the following phenomena: (a) the system pressure response, (b) the natural circulation flows and rates, and (c) the heater rod cladding temperature response. Based on the results of this study, TRAC-BD1/MOD1 can be expected to calculate the thermal-hydraulic behavior of a BWR during a power transient.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6315015
• Report Number(s): EGG-M-18884; CONF-8410142-46; ON: DE85003592
• Resource Relation: Conference: 12. water reactor safety research information meeting, Gaithersburg, MD, USA, 23 Oct 1984; Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

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22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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