Experiment data report for LOFT nonnuclear small break experiment L3-0
Description
Experiment L3-0 was the first Small Break Series L3 experiment conducted at the Loss-of-Fluid Test facility. This experiment was performed to obtain data for analytical code assessment and further understand the thermal-hydraulic behavior which occurs during a postulated loss-of-coolant accident in a pressurized water reactor. The specific objectives of Experiment L3-0 were to (a) determine the break flow rate from available pressurizer pressure and level data, (b) provide data to assess the transient pressure, temperature and density for comparison with predictions from computer codes which model small break transients, (c) determine if chugging occurs in the suppression tank during the small break blowdown, and (d) provide operator training in performing small break experiments. Recorded data for Experiment L3-0 are presented
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A07/MF A01.
Files
Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- 130 p.
- Report number
- NUREG/CR--0959
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11522159
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- HEAT TRANSFER; HYDRAULICS; LOFT REACTOR; LOSS OF COOLANT; MOCKUP; PRESSURE GRADIENTS; REACTOR SAFETY; SPATIAL DISTRIBUTION
- Descriptors DEC
- ACCIDENTS; DISTRIBUTION; ENERGY TRANSFER; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; STRUCTURAL MODELS; TANK TYPE REACTORS; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- TREE--1390.