Published 2002 | Version v1
Computer medium

Coolant void reactivity in a CANDU: A 2-D transport/diffusion comparison

  • 1. Ecole Polytechnique de Montreal, Inst. de genie nucleaire, Montreal, Quebec (Canada)

Description

We have analyzed using diffusion and transport theory methods an axially infinite 2-D representation of a CANDU reactor fueled with 37 element bundles. Our studies indicate that a relatively fine mesh is required to ensure that the reactor model is spatially converged for both diffusion and transport calculations. The effect of using the more physical annular boundary condition in transport is very small while it leads to much higher errors in diffusion. The power distribution computed using diffusion theory are more peaked towards the core center than their transport counterpart with differences reaching 6 % near the core/reflector interface. When full cell homogenization is considered, the differences in the coolant void reactivity between a transport and a diffusion calculation show that the diffusion theory simulates relatively well this effect. On the other hand, using the pin model in transport yields much larger differences in coolant void reactivity. (author)

Part of:
Nuclear power reactors : step into the future. 22nd Canadian Nuclear Society nuclear simulation symposium

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
Imprint Title
Nuclear power reactors : step into the future. 22nd Canadian Nuclear Society nuclear simulation symposium
Imprint Pagination
37.9 Megabytes
Journal Page Range
[15 p.]

Conference

Title
22. Canadian Nuclear Society nuclear simulation symposium
Dates
3-5 Nov 2002
Place
Ottawa, Ontario (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
37004619
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CANDU TYPE REACTORS; COMPUTER CALCULATIONS; DIFFUSION; FUEL ELEMENT CLUSTERS; REACTOR CORES; TRANSPORT
Descriptors DEC
FUEL ASSEMBLIES; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS

Optional Information

Notes
11 refs., 1 tab., 10 figs. Imprint:Available on Compact Disc from the Canadian Nuclear Society, Toronto, Ontario (Canada).