Published 2012 | Version v1
Miscellaneous Metadata-only

Removing fuelling transient using neutron absorbers

Creators

  • 1. Royal Military College of Canada, Chemistry and Chemical Engineering Dept., Kingston, Ontario (Canada)
  • 2. Cameco Fuel Manufacturing, Port Hope, Ontario (Canada)

Description

Preliminary criticality and burnup calculation results indicate that by employing a small amount of neutron absorber the fuelling transient, currently occurring in a CANDU 37-element fuel bundle, can be significantly reduced. A parametric study using the Los Alamos National Laboratories' MCNP 5 code and Atomic Energy of Canada Limited's WIMS-AECL 3.1 is presented in this paper. (author)

Part of:
Building on our past... building for the future. 33rd Annual Canadian Nuclear Society conference and 36th CNS/CNA student conference

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-094
Imprint Title
Building on our past... building for the future. 33rd Annual Canadian Nuclear Society conference and 36th CNS/CNA student conference
Imprint Pagination
189 Megabytes
Journal Page Range
[14 p.]

Conference

Title
33. Annual Canadian Nuclear Society conference; 36. CNS/CNA student conference
Dates
10-13 Jun 2012
Place
Saskatoon, Saskatchewan (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
47018029
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BURNUP; CANDU TYPE REACTORS; CRITICALITY; MONTE CARLO METHOD; NEUTRON ABSORBERS; TRANSIENTS
Descriptors DEC
CALCULATION METHODS; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS

Optional Information

Notes
11 refs., 3 tabs., 11 figs.