Published 2007 | Version v1
Miscellaneous

Simulation of a CANDU reactor approach to criticality after a long shutdown

Creators

  • 1. Univ. of New Brunswick, Fredericton, New Brunswick (Canada)

Description

This study addresses the approach to criticality of CANDU reactors during their startup after a long shutdown. The simulation study is based on the point kinetics model, which represents the prompt neutron kinetics and 17 delayed neutron precursor groups. The parameters of the neutronic model used in this model, are chosen to be the same parameters of Bruce-A reactor fresh core to simulate its start-up. Other dynamics were also included in the model such as the Gadolinium extraction dynamics, and the Xenon dynamics. The factors, which affect the core approach to criticality, have been well simulated and analyzed separately. (author)

Part of:
Embracing the future: Canada's nuclear renewal and growth. 28th annual conference of the Canadian Nuclear Society and 31st CNS/CNA student conference

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
0-919784-88-7
Imprint Title
Embracing the future: Canada's nuclear renewal and growth. 28th annual conference of the Canadian Nuclear Society and 31st CNS/CNA student conference
Imprint Pagination
303 Megabytes
Journal Page Range
[12 p.]

Conference

Title
Canada's nuclear renewal and growth
Acronym
28. Annual conference of the Canadian Nuclear Society and 31. CNS/CNA student conference on embracing the future
Dates
3-6 Jun 2007
Place
Saint John, New Brunswick (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
38107438
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BRUCE SITE; CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; CRITICALITY; NEUTRON TRANSPORT; REACTOR CORES
Descriptors DEC
HEAVY WATER MODERATED REACTORS; NEUTRAL-PARTICLE TRANSPORT; POWER REACTORS; PRESSURE TUBE REACTORS; RADIATION TRANSPORT; REACTOR COMPONENTS; REACTOR SITES; REACTORS; SIMULATION; THERMAL REACTORS

Optional Information

Notes
Paper S1002; 2 refs., 6 tabs., 6 figs.