Published May 1993
| Version v1
Book
Containment isolation in CANDU6 spent fuel transfer system
Description
In the current CANDU-6 plant the fuelling machine D2O system becomes an extension of containment pressure boundary while the fuelling machine is transferring irradiated fuel through spent fuel port to the discharge bay. This method of containment isolation is based on analysis to verify that an acceptable amount of leakage of postulated LOCA transient pressure through fuelling machine can be contained in the spent fuel discharge bay which will not bubble through the water lock between discharge bay and reception bay. This paper presents installation of new Containment Gate as method of containment isolation in this area to meet the AECB C-7 and system impact of this new design in CANDU-6 fuel handling system. (Author)
Additional details
Publishing Information
- Publisher
- Korean Nuclear Society.
- Imprint Place
- Seoul (Korea, Republic of)
- Imprint Title
- Proceeding of the Korean Nuclear Society Spring Meeting
- Imprint Pagination
- 628 p.
- Journal Page Range
- p. 369-373.
Conference
- Title
- The Korean Nuclear Society Spring Meeting.
- Dates
- 21-22 May 1993.
- Place
- Kwangju (Korea, Republic of).
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 26017025
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; CONTAINMENT; LOSS OF COOLANT; PRESSURE CONTROL; PRESSURE DROP; PRESSURE RELEASE; REACTOR CHARGING MACHINES; REACTOR FUELING
- Descriptors DEC
- ACCIDENTS; CONTROL; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS