Published October 1996
| Version v1
Journal article
Simulation experiment study on LOCA at upper plenum of nuclear heating reactor
- 1. Qinghua Univ., Beijing, BJ (China). Inst. of Nuclear Energy Technology
Description
An experiment of small break of upper plenum joint pipe is described. In the test, the system working parameter on conditions that there is rest power after the reactor being shut down were studied at the heating reactor thermohydraulic test system HRTL-5. The effect to nuclear heating reactor safety under break conditions is given
Additional details
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 17
- Journal Issue
- 5
- Journal Page Range
- p. 407-410.
- ISSN
- 0258-0926
- CODEN
- HDGOE6
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 28026138
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BENCH-SCALE EXPERIMENTS; LOSS OF COOLANT; REACTOR SAFETY; SAFETY ANALYSIS; SIMULATION; THR REACTOR
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; POWER REACTORS; PROCESS HEAT REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS