Published 2004
| Version v1
Computer medium
A first attempt at a CANDU-6 core tracking using coupled DRAGON/DONJON calculations
Creators
- 1. Ecole Polytechnique de Montreal, Inst. de Genie Nucleaire, Montreal, Quebec (Canada)
Description
The coupled version of the transport code DRAGON and the diffusion code DONJON has been successfully tested on a realistic CANDU reactor. Our strategy for fuel burnup calculations in DRAGON was improved and is now dependent on the power density. An isotopic content library corresponding to the Gentilly-2 reactor at 3197.9 FPD has been generated using DRAGON. Reactor core calculations have been performed using these history based properties. These results can be used to define error margins for the average parameter cross section generation and the feedback model approach. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 0-919784-80-1
- Imprint Title
- 6. International conference on simulation methods in nuclear engineering
- Imprint Pagination
- 119 Megabytes
- Journal Page Range
- [12 p.]
Conference
- Title
- 6. international conference on simulation methods in nuclear engineering
- Dates
- 12-15 Oct 2004
- Place
- Montreal, Quebec (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 36107457
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CANDU TYPE REACTORS; NEUTRON DIFFUSION EQUATION; NEUTRON TRANSPORT; REACTOR PHYSICS
- Descriptors DEC
- DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; EQUATIONS; HEAVY WATER MODERATED REACTORS; NEUTRAL-PARTICLE TRANSPORT; PARTIAL DIFFERENTIAL EQUATIONS; PHYSICS; POWER REACTORS; PRESSURE TUBE REACTORS; RADIATION TRANSPORT; REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 13 refs., 3 tabs., 5 figs.