Water hammer in the circulating pipe line with pressure vessels
- 1. Ibaraki Univ., Hitachi (Japan). Faculty of Engineering
Description
Studies have been made to compare and discuss the analytical solutions solved by the method of characteristics with the experimental results on the water hammer. The measurements have been carried out using the 1/6 scale model of the primary coolant system of the experimental fast breeder reactor ''JOYO'' belonging to Power Reactor and Nuclear Fuel Development Corporation. The water hammer has been taken place, at the flow velocity 0.5 and 1.0 m/sec, with closing slowly the flow control clap valve in the time ranges 4.5 -- 9.6 seconds and 4.6 -- 11.2 seconds respectively. Qualitative agreement was found between the analytical and experimental results. And the calculation gave the safety value at the peak pressure. Therefore the calculation models and idea used in this paper have sufficient practical value. (author)
Additional details
Publishing Information
- Journal Title
- Nippon Kikai Gakkai Ronbunshu, B Hen
- Journal Volume
- 49
- Journal Issue
- 446
- Series
- Nippon Kikai Gakkai Ronbunshu, B Hen.
- Journal Page Range
- 2236-2241
- ISSN
- 0387-5016
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 16031420
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ANALYTICAL SOLUTION; BOUNDARY CONDITIONS; FLOW RATE; JOYO REACTOR; NUMERICAL SOLUTION; PIPELINES; PRESSURE DEPENDENCE; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; TIME DEPENDENCE; WATER HAMMER
- Descriptors DEC
- BREEDER REACTORS; CONTAINERS; COOLING SYSTEMS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS