Published May 2012 | Version v1
Miscellaneous

Determination of the Pipe Diameter and Length of a Sodium Experimental Installation for Single Phase Natural Convection Simulations

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

Description

As a part of the verification of PDRC(Passive Decay heat Removal Circuit) concept of DSFR(Demonstration Sodium-cooled Fast Reactor), KAERI will design and construct a large-scale sodium integral effect test facility called STELLA. This paper describes the selection method of the pipe of the experimental model installation, which should be designed so as to simulate various thermal-hydraulic features including the transient with natural convection heat transfer in the prototype. The scaling ratio of the model is one-fifth of the length scale, and the ratio of the temperature rise(ΔToR ) through the heat exchanger is the same with the same coolant as of the prototype

Part of:
Proceedings of Korean Nuclear Society, Daejeon (KR)

Additional details

Publishing Information

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

Conference

Title
2012 spring meeting of the KNS
Dates
16-18 May 2012
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
43073291
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
AFTER-HEAT REMOVAL; COMPUTERIZED SIMULATION; DESIGN; HEAT EXCHANGERS; NATURAL CONVECTION; PIPES; S CODES; SODIUM COOLED REACTORS; TEST FACILITIES; THERMAL HYDRAULICS; VERIFICATION
Descriptors DEC
COMPUTER CODES; CONVECTION; ENERGY TRANSFER; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; LIQUID METAL COOLED REACTORS; MASS TRANSFER; MECHANICS; REACTORS; REMOVAL; SIMULATION; TUBES

Optional Information

Notes
4 refs, 1 fig, 1 tab