Published October 1986 | Version v1
Miscellaneous

TRIVAC: a model diffusion code for fuel management and design applications

Creators

  • 1. Ecole Polytechnique, Montreal, PQ (Canada)

Description

A new three dimensional neutron diffusion code named TRIVAC was set up using advanced discretization algorithms and improved iteration strategies. The two variable order discretization algorithms used in TRIVAC are based respectively on the variational and nodal collocation techniques. These algorithms produce reconstructible solutions which are upper and lower limits of the exact solution. The eigenvalue matrix system is solved using an ADI preconditioning of the power method in conjunction with a symmetric variational acceleration technique. Validation results are reported for the IAEA two- and three-dimensional benchmarks and for a two-dimensional PWR

Part of:
Proceedings of the 2. international conference on simulation methods in nuclear engineering

Additional details

Publishing Information

ISBN
0-919784-11-9
Imprint Title
Proceedings of the 2. international conference on simulation methods in nuclear engineering
Imprint Pagination
950 p.
Journal Page Range
p. 257-277.
Report number
INIS-mf--12868(v.1,2)

Conference

Title
2. International conference on simulation methods in nuclear engineering.
Dates
14-16 Oct 1986.
Place
Montreal, PQ (Canada).

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
22064285
Subject category
S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; NEUTRON TRANSPORT THEORY; POLYNOMIALS; T CODES; VARIATIONAL METHODS
Descriptors DEC
COMPUTER CODES; FUNCTIONS; RADIATION FLUX; TRANSPORT THEORY

Optional Information