Experiment data report for semiscale Mod-1 test S-06-6 (LOFT counterpart test)
Description
Recorded test data are presented for Test S-06-6 of the Semiscale Mod-1 LOFT counterpart test series. These tests are among several Semiscale Mod-1 experiments conducted to investigate the thermal and hydraulic phenomena accompanying a hypothesized loss-of-coolant accident in a pressurized water reactor (PWR) system. Test S-06-6 was conducted from initial conditions of 15 792 kPa and 563 K to investigate the response of the Semiscale Mod-1 system to a depressurization and reflood transient following a simulated double-ended offset shear of the broken loop cold leg piping. During the test, cooling water was injected into the cold leg of the intact loop to simulate emergency core coolant injection in a PWR. The heater rods in the electrically heated core were operated at an axial peak power density which was 75% of the maximum peak power density (52.5 kW/m). Test S-06-6 also evaluated the effect of special hardware assumptions on the core response
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A13/MF A01.Files
9362917.pdf
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Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- 285 p.
- Report number
- TREE-NUREG--1126
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 9362917
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ECCS; FLOW RATE; HEAT TRANSFER; HYDRAULICS; LIQUID FLOW; LOSS OF COOLANT; MOCKUP; PRESSURE GRADIENTS; PWR TYPE REACTORS; REACTOR SAFETY; SIMULATION; SPATIAL DISTRIBUTION
- Descriptors DEC
- ACCIDENTS; DISTRIBUTION; ENERGY TRANSFER; FLUID FLOW; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; STRUCTURAL MODELS; WATER COOLED REACTORS; WATER MODERATED REACTORS