Published May 2011 | Version v1
Miscellaneous Metadata-only

Radionuclide Release after Channel Flow Blockage Accident in CANDU-6 Plant

Creators

  • 1. Korea Electric Power Corporation Research Institute, Daejeon (Korea, Republic of)

Description

The channel flow blockage accident is one of the in core loss of coolant accidents, the release path of radionuclide is very different from conventional loss of coolant accidents. The large amount of radionuclide released from broken channel is being washed during it passes through the moderator in Calandria. The objective of containment behavior analysis for channel flow blockage event is to assess the amount of radionuclide release to the ambient atmosphere. Radionuclide release rates in case of channel flow blockage with all safety system available, that is containment building is intact, as well as with containment system impairment are analyzed with GOTHIC and SMART code

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS spring meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2011 spring meeting of the KNS
Dates
26-27 May 2011
Place
Taebaek (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
42099183
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CALANDRIAS; CANDU TYPE REACTORS; CONTAINMENT; ENGINEERED SAFETY SYSTEMS; FLOW BLOCKAGE; G CODES; LOSS OF COOLANT; RADIOISOTOPES; S CODES
Descriptors DEC
ACCIDENTS; COMPUTER CODES; CONTAINERS; HEAVY WATER MODERATED REACTORS; ISOTOPES; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS

Optional Information

Notes
3 refs, 6 figs