Published 2005 | Version v1
Miscellaneous

Development of a three-field model for two-phase annular-mist flow

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

Description

The widely used safety analysis codes such as RELAP5 and TRAC use two-phase, two-field representation to describe the thermal-hydraulic phenomena of nuclear power plant. But the averaged description of liquid phase is significantly different from actual phenomena especially when droplet entrainment exists. On the other hand, COBRA-TF, which describes the entrainment field as a separate one from continuous liquid film, is showing the advanced features for the thermal-hydraulics codes but its applicability is highly restricted to the reactor core. Recently, USNRC is developing a thermal-hydraulic analysis code that consolidates the capabilities of various codes and TRAC-M is the base of the efforts. With this situation, the implementation of three-field modeling into TRAC-M/F90 is necessary and as for the first application, the implementation into one-dimensional component is presented

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

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

Conference

Title
2005 spring meeting of the KNS
Dates
26-27 May 2005
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
37041715
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ENTRAINMENT; NUCLEAR POWER PLANTS; R CODES; SAFETY ANALYSIS; T CODES; THERMAL HYDRAULICS; TWO-PHASE FLOW
Descriptors DEC
COMPUTER CODES; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS

Optional Information

Notes
10 refs, 1 fig, 1 tab