Published June 2009 | Version v1
Miscellaneous Metadata-only

Assessment of applicability of TRAC-BF1 for thermal hydraulic instability

Creators

  • 1. Japan Atomic Energy Agency, Tokai, Ibaraki (Japan)

Description

To assess the stability of advanced light water reactors or steam generators in FBR, JAEA has been developing a prediction method for thermal-hydraulic instability based on system analysis code TRAC-BF1. In the present paper, thermal-hydraulic instability experiments were analyzed with TRAC-BF1 code and the applicability of the code for thermal-hydraulic instability was estimated. The heat flux of the boundary between stable and unstable region is in agreement with the experimental data within about 10% of error. The onset of instability can be predicted with TRAC-BF1. (author)

Part of:
The 14th national symposium on power and energy systems (SPES 2009)

Additional details

Publishing Information

Imprint Title
The 14th national symposium on power and energy systems (SPES 2009)
Imprint Pagination
536 p.
Journal Page Range
p. 117-118

Conference

Title
14. national symposium on power and energy systems
Acronym
SPES 2009
Dates
29-30 Jun 2009
Place
Tsukuba, Ibaraki (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
44012123
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COOLANTS; FBR TYPE REACTORS; HEAT FLUX; INSTABILITY; OSCILLATIONS; SATURATION; STEAM GENERATORS; T CODES; TEMPERATURE DEPENDENCE; THERMAL HYDRAULICS; WATER COOLED REACTORS
Descriptors DEC
BOILERS; BREEDER REACTORS; COMPUTER CODES; EPITHERMAL REACTORS; FAST REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; REACTORS; VAPOR GENERATORS

Optional Information

Notes
4 refs., 5 figs.