Hydraulic Design and Evaluation of the PHTS Mechanical Pump of PGSFR
- 1. Korea Atomic Energy Research Institute (KAERI), Daejeon (Korea, Republic of)
Description
The hydraulic parts of the primary pump for the Prototype Generation IV Sodium-Cooled Fast Reactor were designed at the Korea Atomic Energy Research Institute. The hydraulic parts, such as the impeller and diffuser, of the primary heat transfer system pump were designed to satisfy the hydraulic performance requirements. The essential geometric parameters of the impeller and diffuser were determined using optimal design methodology. To verify the performance of the pump, and to produce safety analysis input data, a scaled down model pump and test facility were designed and fabricated based on the scaling law. The hydraulic performance of model pump was tested in water under empirical, theoretical and conservative assumptions. The performance curve, net positive suction head curve and homologous curve were obtained from the model pump test facility. The hydraulic performance, with a rational design margin, was verified from the model pump test. (author)
Additional details
Identifiers
Publishing Information
- Publisher
- IAEA
- Imprint Place
- Vienna (International Atomic Energy Agency (IAEA))
- ISBN
- 978-92-0-108618-1
- Imprint Title
- Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17). Proceedings of an International Conference. Companion CD-ROM
- Imprint Pagination
- [1 CD-ROM]
- Series
- Proceedings Series
- Journal Page Range
- 10 p.
- ISSN
- 0074-1884
Conference
- Title
- International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development
- Acronym
- FR17
- Dates
- 26-29 Jun 2017
- Place
- Yekaterinburg (Russian Federation)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51006193
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DIFFUSERS; GEOMETRY; HEAT TRANSFER; HYDRAULICS; KAERI; REACTOR DESIGN; SAFETY ANALYSIS; SCALING LAWS; SODIUM COOLED REACTORS; TEST FACILITIES
- Descriptors DEC
- DESIGN; ENERGY TRANSFER; FLUID MECHANICS; KOREAN ORGANIZATIONS; LIQUID METAL COOLED REACTORS; MATHEMATICS; MECHANICS; NATIONAL ORGANIZATIONS; REACTOR LIFE CYCLE; REACTORS
Optional Information
- Notes
- 9 refs., 7 figs., 1 tab. Imprint:refs., figs., tabs.
- Secondary number(s)
- IAEA-CN--245-308