Published 2003 | Version v1
Report Metadata-only

Main pipe rupture accident analysis for China experimental fast reactor

Creators

  • 1. China Institute of Atomic Energy, Beijing (China)
  • 2. China Institute of Atomic Energy, Beijing (CN)

Description

The main pipe rupture accident is the most serious one for the lost of coolant accident of the pool type sodium cooled FBR (Fast Breeder Reactor). To simulate this accident, a model is developed based on the OASIS code, which is a French fast reactor system safety analysis code. To abide by the strictly accident analysis principles, the main pipe rupture accident is calculated to various position of the pipe. Accident sequence and key parameters including the fuel cladding temperature of reactor are obtained for each case. The calculation results show that the fuel cladding temperature is under the safety limitation and the coolant temperature is lower then the saturation temperature of sodium in all cases. (author)

Part of:
Technical meeting on 'Primary coolant pipe rupture event in liquid metal cooled fast reactors'. Working material

Additional details

Publishing Information

Imprint Title
Technical meeting on 'Primary coolant pipe rupture event in liquid metal cooled fast reactors'. Working material
Imprint Pagination
375 p.
Journal Page Range
p. 278-286
Report number
IAEA-TM--26027

Conference

Title
IAEA-TWGFR technical meeting on 'Primary coolant pipe rupture event in liquid metal cooled fast reactors'
Dates
13-17 Jan 2003
Place
Kalpakkam (India)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
34055000
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
LMFBR TYPE REACTORS; LOSS OF COOLANT; O CODES; RUPTURES; SODIUM; SODIUM COOLED REACTORS; TEMPERATURE DEPENDENCE
Descriptors DEC
ACCIDENTS; ALKALI METALS; BREEDER REACTORS; COMPUTER CODES; ELEMENTS; EPITHERMAL REACTORS; FAILURES; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; METALS; REACTOR ACCIDENTS; REACTORS

Optional Information

Notes
Presentation of paper on p. 124-151; 2 refs, 11 figs, 2 tabs Imprint:Web site: http://www.iaea.org/inis/aws/fnss/twgfr/working_materials.html
Secondary number(s)
TWG-FR--112