Published October 2009
| Version v1
Miscellaneous
The Assessment of Fuel Channel behavior in LOCA for CANDU NPP
Description
Large loss of coolant accident (LOCA) is the most limiting accident in terms of the amount of damaged fuels in CANDU reactors. The accident assumes pipe break in the reactor header which is large pipe in primary coolant system. The amount of fuel failure determines the source term for dose in the environment. Fuel failure is dependent on the channel flow behavior which determines the temperature of fuel and fuel channel. Detailed study on the fuel channel can help to understand the fuel behavior in LOCA. Here detailed behavior of fuel channels in reactor inlet header (RIH) 35% break is considered
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2009 autumn meeting of the KNS
- Dates
- 29-30 Oct 2009
- Place
- Kyungju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 41027284
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CANDU TYPE REACTORS; COOLING SYSTEMS; FAILURES; FUEL CHANNELS; LOSS OF COOLANT; NUCLEAR POWER PLANTS; PIPES; SOURCE TERMS
- Descriptors DEC
- ACCIDENTS; ENERGY SYSTEMS; HEAVY WATER MODERATED REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; TUBES
Optional Information
- Notes
- 3 refs, 6 figs, 2 tabs