Published May 2015 | Version v1
Miscellaneous

Performance Evaluation of a Printed Circuit Steam Generator for Integral Reactors: A Feasibility Test

  • 1. KAERI, Daejeon (Korea, Republic of)
  • 2. Alfa Laval Korea Ltd., Daejeon (Korea, Republic of)

Description

SMART (System-integrated Modular Advanced ReacTor) is a small-sized integral type pressurized water reactor. It adopts advanced design features such as structural safety improvement, system simplification, and component modularization to achieve highly enhanced safety and improved economics. The design issues related to further safety enhancement and cost reduction have received significant attention to increase its competitiveness in the global small reactor market. For the cost reduction, it is important to design the reactor vessel as small as possible. Thus, it is necessary to reduce the volume of main components such as a steam generator. Its manufacturing processes of the chemical etching and diffusion bonding provide high effectiveness, high compactness, and inherent structural safety under high temperatures and high pressures. Thus, it is expected to be an alternative to the conventional shell and tube type steam generator in SMART. In this paper, simple thermal-hydraulic performance measurement of a small-scale printed circuit steam generator (PCSG) is conducted to investigate the feasibility of applying it to SMART. The simple thermal-hydraulic performance of the PCSG has been experimentally evaluated. A small-scale PCHE is employed to investigate the feasibility of operating it as a steam generator. The performance assessment reveals that the PCSG stably produces superheated steam, and the increased degree of superheat is obtained at lower water flow rate. However, the flow instability is increased with the decrease of the water flow rate. Thus, it is required to apply the orifice design into the cold side plate to suppress the density-wave oscillations. The pressure drops and heat transfer rates increase with the water flow rate

Part of:
Proceedings of the KNS 2015 Spring Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2015 spring meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[3 p.]

Conference

Title
2015 spring meeting of the KNS
Dates
6-8 May 2015
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
47023279
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
DESIGN; FLOW RATE; HEAT EXCHANGERS; PERFORMANCE; PRESSURE DROP; PRINTED CIRCUITS; PWR TYPE REACTORS; STEAM GENERATORS
Descriptors DEC
BOILERS; ELECTRONIC CIRCUITS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
5 refs, 5 figs