Published October 2016 | Version v1
Miscellaneous

Development of platform to compare different wall heat transfer packages for system analysis codes

  • 1. KAIST, Daejeon (Korea, Republic of)
  • 2. Hanyang University, Seoul (Korea, Republic of)

Description

System thermal hydraulic (STH) analysis code is used for analyzing and evaluating the safety of a designed nuclear system. The system thermal hydraulic analysis code typically solves mass, momentum and energy conservation equations for multiple phases with sets of selected empirical constitutive equations to close the problem. Several STH codes are utilized in academia, industry and regulators, such as MARS-KS, SPACE, RELAP5, COBRA-TF, TRACE, and so on. Each system thermal hydraulic code consists of different sets of governing equations and correlations. However, the packages and sets of correlations of each code are not compared quantitatively yet. Wall heat transfer mode transition maps of SPACE and MARS-KS have a little difference for the transition from wall nucleate heat transfer mode to wall film heat transfer mode. Both codes have the same heat transfer packages and correlations in most region except for wall film heat transfer mode. Most of heat transfer coefficients calculated for the range of selected variables of SPACE are the same with those of MARS-KS. For the intervals between 500K and 540K of wall temperature, MARS-KS selects the wall film heat transfer mode and Bromley correlation but SPACE select the wall nucleate heat transfer mode and Chen correlation. This is because the transition from nucleate boiling to film boiling of MARS-KS is earlier than SPACE. More detailed analysis of the heat transfer package and flow regime package will be followed in the near future

Part of:
Proceedings of the KNS 2016 Autumn Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2016 Autumn Meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[3 p.]

Conference

Title
2016 Autumn Meeting of the KNS
Dates
26-28 Oct 2016
Place
Kyungju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
48067474
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CORRELATIONS; ENERGY CONSERVATION; EQUATIONS; HEAT TRANSFER; M CODES; NUCLEATE BOILING; S CODES; SAFETY; THERMAL HYDRAULICS
Descriptors DEC
BOILING; COMPUTER CODES; ENERGY TRANSFER; FLUID MECHANICS; HYDRAULICS; MECHANICS; PHASE TRANSFORMATIONS

Optional Information

Notes
3 refs, 2 figs, 4 tabs