Published May 1999
| Version v1
Miscellaneous
Preliminary ROP assessment for CANDU-6 with DUPIC fuel
Creators
- 1. KAERI, Taejon (Korea, Republic of)
- 2. Atomic Energy of Canada Limited, Ontario (Canada)
Description
Preliminary assessments for regional overpower protection trip system of the CANDU-6 reactor with DUPIC fuel has been performed. For this study, some severe flux perturbation cases were selected, and the trip setpoint was calculated. In addition to the trip set point, some sensitivity studies for uncertainty of the channel random and common-random were performed. This study has shown that the trip setpoint of the DUPIC fuel core is slightly improved compared to the natural uranium fuel core with the same uncertainties of natural uranium core
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the Korean Nuclear Society spring meeting
- Imprint Pagination
- [one CD-ROM]
- Journal Page Range
- [11 p.]
Conference
- Title
- 1999 spring meeting of the Korean Nuclear Society
- Dates
- 28-29 May 1999
- Place
- Pohang (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 33042405
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CANDU TYPE REACTORS; CHARGES; COMPUTER CALCULATIONS; REACTOR CORES; SPENT FUELS; URANIUM
- Descriptors DEC
- ACTINIDES; ELEMENTS; ENERGY SOURCES; FUELS; HEAVY WATER MODERATED REACTORS; MATERIALS; METALS; NUCLEAR FUELS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 5 refs, 3 figs, 5 tabs