Test results on direct containment heating by high-pressure melt ejection into the Surtsey vessel: The TDS test series
- Sandia National Lab., Albuquerque, NM (United States). Severe Accident Phenomenology
The Technology Development and Scoping (TDS) test series was conducted to test and develop instrumentation and procedures for performing steam-driven, high-pressure melt ejection (HPME) experiments at the Surtsey Test Facility to investigate direct containment heating (DCH). Seven experiments, designated TDS-1 through TDS-7, were performed in this test series. These experiments were conducted using similar initial conditions; the primary variable was the initial pressure in the Surtsey vessel. All experiments in this test series were performed with a steam driving gas pressure of {approx_equal} 4 MPa, 80 kg of lumina/iron/chromium thermite melt simulant, an initial hole diameter of 4.8 cm (which ablated to a final hole diameter of {approx_equal} 6 cm), and a 1/10th linear scale model of the Surry reactor cavity. The Surtsey vessel was purged with argon (<0.25 mol% O{sub 2}) to limit the recombination of hydrogen and oxygen, and gas grab samples were taken to measure the amount of hydrogen produced.
- Research Organization:
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-94AL85000
- OSTI ID:
- 10183168
- Report Number(s):
- SAND-91-1208; ON: DE94019086; BR: GB0103012; TRN: 94:019037
- Resource Relation:
- Other Information: PBD: Aug 1994
- Country of Publication:
- United States
- Language:
- English
Similar Records
The third integral effects test (IET-3) in the Surtsey Test Facility
The Integral Effects Test (IET-1) in the Surtsey Test Facility
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
MELTDOWN
TEST FACILITIES
CONTAINMENT BUILDINGS
HEATING
PRESSURIZATION
CORIUM
MITIGATION
RELIABILITY
SCALE MODELS
BLOWDOWN
EXPERIMENTAL DATA
220900
210200
REACTOR SAFETY
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED