Published July 1991 | Version v1
Report Open

Development of design technology for an advanced pressurized water reactor

Creators

  • 1. Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)

Description

The objective of the project is to localize technology for the improvement of the reactor coolant system through a multidimensional thermal-hydraulic analysis for the steam generator and the pressurizer. Flow distribution analysis has been done for the YGN 3/4 steam generators when steady-state output conditions were varied in the ranges such as 100, 75, 50, and 25 using three-dimensional ATHOS 3 code. The results of the thermal-hydraulic analysis have been used for flow-induced vibration analysis for the YGN 3/4 steam generators. ATHOS 3 code has been modified for YGN 3/4 steam generator tube lane region using the cartesian geometry and the local porosity in the boundaries of the two adjacent cells. Stability ratio for the tube vibration has been calculated the modified ATHOS 3 and ANSYS code. A sensitivity study for the pressurizer volume change has been analyzed using LTC code which is for the performance analysis to predict an optimistic pressurizer volume. (Author)

Availability note (English)

MF available from INIS under the Report Number.

Files

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Additional details

Additional titles

Subtitle (English)
Improvements of the reactor coolant system

Publishing Information

Imprint Pagination
167 p.
Report number
KAERI/RR--994/91

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
23083577
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
COMPUTER CODES; FLUID FLOW; HEAT EXCHANGERS; MECHANICAL VIBRATIONS; PIPES; PRESSURE DROP; PRESSURIZERS; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS
Descriptors DEC
COOLING SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS