Using environment dependent cell properties for ACR-1000 core calculations
Creators
- 1. Inst. de genie nucleaire, Ecole Polytechnique de Montreal, Montreal, Quebec (Canada)
Description
The Advanced CANDU Reactor (ACR-1000) is a generation III+ heavy water moderated and light water cooled reactor. It is designed to meet very strict requirements related to safety and competitive cost. The differences between the CANDU-6 and the ACR include the use of light water coolant, low-enriched uranium fuel and a major reduction in the cell lattice pitch. In fact, reducing of the lattice pitch should have a large impact on the neutrons behavior in the reactor because the cells will be more strongly coupled. The purpose of the article is to evaluate the impact of using environment dependent cell cross sections and leakage coefficient on a full core simulation of the ACR-1000. The DRAGON code will be used to obtain two-group nuclear properties. Those properties will then be used to perform a full core simulation of the ACR-1000 with the DONJON code. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 0-919784-91-7
- Imprint Title
- Towards the next generation of simulation tools. 23rd Canadian Nuclear Society nuclear simulation symposium
- Imprint Pagination
- 29 Megabytes
- Journal Page Range
- [15 p.]
Conference
- Title
- 23. Canadian Nuclear Society nuclear simulation symposium
- Dates
- 2-4 Nov 2008
- Place
- Ottawa, Ontario (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 40098793
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CANDU TYPE REACTORS; HWLWR TYPE REACTORS; NEUTRON TRANSPORT; REACTOR LATTICES; SLIGHTLY ENRICHED URANIUM; WATER COOLED REACTORS
- Descriptors DEC
- ACTINIDES; ELEMENTS; ENRICHED URANIUM; HEAVY WATER MODERATED REACTORS; ISOTOPE ENRICHED MATERIALS; MATERIALS; METALS; NEUTRAL-PARTICLE TRANSPORT; POWER REACTORS; PRESSURE TUBE REACTORS; RADIATION TRANSPORT; REACTORS; THERMAL REACTORS; URANIUM; WATER COOLED REACTORS
Optional Information
- Notes
- 9 refs., 5 tabs., 10 figs.