Published May 2014 | Version v1
Miscellaneous

Validation of Two-group IAT (Interfacial Area Transport) Model for Droplet Field in SPACE Code

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

Description

In SPACE (Safety and Performance Analysis Code for Nuclear Power Plant) code model, interfacial area concentration of the droplet field is of importance for estimation of the interfacial momentum and heat transfer between the droplet and the vapor phases. In this study, to enhance the prediction capability for the interfacial area and reflect the dynamic behavior of interface between the droplet and the spacer grid, IAT (Interfacial Area Transport) model was implemented in the SPACE code. Two-group IAT equation model was implemented in the SPACE code to mechanistically estimate dynamic behavior of the interfacial area for the droplet. The breakup of the droplet by impacting on the spacer grid was considered as major source terms in the equation. Variation of the interfacial area for the large and small droplets could be quantitatively estimated with separated transport equations for two groups. The IAT model for the droplet field in the SPACE code was validated with comparison to FLECHT-SEASET experiment. The calculation result proved that the droplet IAT model has estimated the dynamic behavior of the droplet interfacial area and reduced the vapor temperature by increasing the amount of the vaporization. For the further study, development of more precise model for the droplet breakup is required with comparison of the droplet size to the test result

Part of:
Proceedings of the KNS 2014 spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2014 spring meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[3 p.]

Conference

Title
2014 spring meeting of the KNS
Dates
28-30 May 2014
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
46050506
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
DROPLETS; EQUATIONS; EVAPORATION; FLUID FLOW; INTERFACES; NUCLEAR POWER PLANTS; S CODES; SAFETY ANALYSIS; THERMAL HYDRAULICS; VALIDATION
Descriptors DEC
COMPUTER CODES; FLUID MECHANICS; HYDRAULICS; MECHANICS; NUCLEAR FACILITIES; PARTICLES; PHASE TRANSFORMATIONS; POWER PLANTS; TESTING; THERMAL POWER PLANTS

Optional Information

Notes
3 refs, 4 figs, 1 tab