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Published October 2009 | Version v1
Miscellaneous

Estimation on the Pressure Loss of the Conceptual Primary Cooling System and Design of the Primary Cooling Pump for a Research Reactor

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

A new conceptual primary cooling system (PCS) for a research reactor has been designed for an adequate cooling to the reactor core which has various powers ranging from 30MW through 80MW. The developed primary cooling system consisted of decay tanks, pumps, heat exchangers, vacuum breakers, some isolation and check valves, connection piping, and instruments. Because the system flow rate should be determined by the thermal hydraulic design analysis for the core, the heads to design the primary cooling pumps (PCPs) in a PCS will be estimated by the variable system flow rates. The heads of the part of a research reactor vessel was evaluated by the previous study. The various pressure losses of the PCS can be calculated by the dimensional analysis of the pipe flow and the head loss coefficient of the components. The purpose of this research is to estimate the various pressure losses and to design the PCPs

Part of:
Transactions of the Korean Nuclear Society Autumn Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS autumn meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2009 autumn meeting of the KNS
Dates
29-30 Oct 2009
Place
Kyungju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
41027081
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
DESIGN; FLOW RATE; PUMPS; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR VESSELS; RESEARCH REACTORS; THERMAL HYDRAULICS
Descriptors DEC
CONTAINERS; COOLING SYSTEMS; ENERGY SYSTEMS; EQUIPMENT; FLUID MECHANICS; HYDRAULICS; MECHANICS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS

Optional Information

Notes
3 refs, 3 figs, 5 tabs