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