Published December 2018 | Version v1
Book

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)

Part of:
Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17). Proceedings of an International Conference. Companion CD-ROM

Additional details

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