Published 2008 | Version v1
Book Metadata-only

Efficiency of the delta-tracking technique for Monte Carlo calculations applied to neutron-transport simulations of the advanced Candu reactor design

Creators

  • 1. Atomic Energy of Canada Limited, Chalk River (Canada)
  • 2. Commissariat a l'Energie Atomique, Saint-Paul-lez-Durance (France)
  • 3. Ecole Polytechnique de Montreal, Montreal (Canada)

Description

The paper presents the results of a first implementation of a Monte Carlo module in DRAGON Version 4 based on the delta-tracking technique. The Monte Carlo module uses the geometry and the self-shielded multigroup cross-sections calculated with a deterministic model. The module has been tested with three different configurations of an ACRTM-type lattice. The paper also discusses the impact of this approach on the efficiency of the Monte Carlo module. (authors)

Additional details

Publishing Information

Publisher
Paul Scherrer Institut - PSI
Imprint Place
Villigen PSI (Switzerland)
ISBN
978-3-9521409-5-6
Imprint Pagination
8 p.

Conference

Title
International Conference on the Physics of Reactors 'Nuclear Power: A Sustainable Resource'
Acronym
PHYSOR'08
Dates
14-19 Sep 2008
Place
Interlaken (Switzerland)

INIS

Country of Publication
Switzerland
Country of Input or Organization
France
INIS RN
41116103
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CANDU TYPE REACTORS; CONFIGURATION; CROSS SECTIONS; DESIGN; EFFICIENCY; GEOMETRY; IMPLEMENTATION; MONTE CARLO METHOD; NEUTRON TRANSPORT; SIMULATION
Descriptors DEC
CALCULATION METHODS; HEAVY WATER MODERATED REACTORS; MATHEMATICS; NEUTRAL-PARTICLE TRANSPORT; POWER REACTORS; PRESSURE TUBE REACTORS; RADIATION TRANSPORT; REACTORS; THERMAL REACTORS

Optional Information

Notes
16 refs.; proceedings are available as a CD-ROM on request to info'at'physor08.ch