Published April 2005 | Version v1
Computer medium Metadata-only

Development of next generation PWR (APWR+). Examination of natural circulation and heat removal by steam generator

Creators

  • 1. Kansai Electric Power Co., Inc., Osaka (Japan)
  • 2. Kyushu Electric Power Co., Inc., Fukuoka (Japan)
  • 3. Japan Atomic Power Company, Tokyo (Japan)
  • 4. Mitsubishi Heavy Industries, Ltd., Tokyo (Japan)

Description

Next generation PWR (APWR+) chooses plant design to introduce secondary steam depressurization and the decay heat removal using steam generators (SG) during small break loss of coolant accident (LOCA). The system pressure can be reduced rapidly, and then boric acid water can be injected from accumulators earlier than the current safety system to end the accident. In order to examine natural circulation and heat removal by SG, two-phase flow tests through reverse U-tube of SG and validation of two-phase natural circulation analysis code were conducted, which could verify the safety concept of APWR+. (T. Tanaka)

Part of:
The thermal and nuclear power generation convention 2004 Hiroshima

Additional details

Publishing Information

Publisher
Thermal and Nuclear Power Engineering Society
Imprint Place
Tokyo (Japan)
Imprint Title
The thermal and nuclear power generation convention 2004 Hiroshima
Imprint Pagination
328 p.
Journal Page Range
p. 183-188

Conference

Title
The thermal and nuclear power generation convention 2004
Dates
27-29 Oct 2004
Place
Hiroshima (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
39089424
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AFTER-HEAT REMOVAL; C CODES; COOLING; DEPRESSURIZATION; LOSS OF COOLANT; NATURAL CONVECTION; NITROGEN; PWR TYPE REACTORS; SAFETY ANALYSIS; SECONDARY COOLANT CIRCUITS; STEAM GENERATORS; TANKS; TWO-PHASE FLOW; VALIDATION
Descriptors DEC
ACCIDENTS; BOILERS; COMPUTER CODES; CONTAINERS; CONVECTION; COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; HEAT TRANSFER; MASS TRANSFER; NONMETALS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; REMOVAL; TESTING; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name pdf, Paper ID 1201.pdf; 4 refs., 12 figs., 2 tabs.