Published May 2018 | Version v1
Miscellaneous

Development of a Thermal-Hydraulic Analysis Code for an IHX-Combined Steam Generator with Serpentine Tube Bundles

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
  • 2. POSTECH, Pohang (Korea, Republic of)
  • 3. Chungang University, Seoul (Korea, Republic of)

Description

An sodium-cooled fast reactor (SFR) can have enhanced safety features by using liquid sodium as a coolant, but there is concern about unexpected events coming from a sodium water reaction (SWR) in a Rankine cycle steam generator. Several prior researchers have suggested innovative concepts of the integrated type steam generators including an intermediate heat exchanger (IHX) for the purpose of inherently elimination of SWR by employing intermediate fluid between liquid sodium and steam/water system. In this study, we propose a new IHX-combined steam generator with a serpentine tube configuration (Serpentine tube type IHX-Combined Steam Generator, S-ICSG), and reports the developed thermal-hydraulic analysis code for specific design evaluation of the S-ICSGs (SPINS-S, Sizing and Performance Analyzer for an Integrated Steam Generator – Serpentine tube arrangement). The new IHX-Combined Steam Generator concept having serpentine tube configuration (S-ICSG) was proposed in this work. It has the advantage of using the proven power conversion system of the existing Rankine cycle while it can prevent the SWR by adopting the inactive intermediate fluid with both sodium and water. We developed the thermal-hydraulic performance analysis code, and the test results were described.

Part of:
Proceedings of the KNS 2018 Spring Meeting

Additional details

Identifiers

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2018 Spring Meeting
Imprint Pagination
vp.
Journal Page Range
[3 p.]

Conference

Title
2018 Spring Meeting of the KNS
Dates
16-18 May 2018
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
50059156
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTER CODES; COOLANTS; HEAT TRANSFER; SAFETY; SODIUM COOLED REACTORS; SPENT FUELS; STEAM GENERATORS; THERMAL HYDRAULICS; TUBES
Descriptors DEC
BOILERS; ENERGY SOURCES; ENERGY TRANSFER; FLUID MECHANICS; FUELS; HYDRAULICS; LIQUID METAL COOLED REACTORS; MATERIALS; MECHANICS; NUCLEAR FUELS; REACTOR MATERIALS; REACTORS; VAPOR GENERATORS

Optional Information

Notes
4 refs, 2 figs, 5 tabs