Published May 2008
| Version v1
Miscellaneous
Neutronic Impact of Pressure Tube Creep in a CANDU Lattice
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
In the CANDU reactor, the coolant channel diameter increases due to the pressure tube creep resulting from neutron irradiation damage. Along with the creep, the pressure tube also undergoes a slight sagging phenomenon. It is well known that a crept pressure tube leads to a non-uniform coolant flow causing a concern in the fuel cooling. In this work, the pressure tube creep was evaluated from the neutronic point of view with the HELIOS code. Impact of the crept pressure tube is evaluated in terms of the lattice reactivity, void reactivity, pin-wise power, atom density of plutonium isotopes, and fuel temperature coefficient
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
- 2008 spring meeting of the KNS
- Dates
- 29-30 May 2008
- Place
- Kyeongju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 39109042
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CANDU TYPE REACTORS; COOLANTS; CREEP; H CODES; IRRADIATION; PLUTONIUM; PRESSURE TUBES; REACTIVITY
- Descriptors DEC
- ACTINIDES; COMPUTER CODES; ELEMENTS; HEAVY WATER MODERATED REACTORS; MECHANICAL PROPERTIES; METALS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS; TRANSURANIUM ELEMENTS; TUBES
Optional Information
- Notes
- 2 refs, 6 figs