Published 1993 | Version v1
Journal article

Neutron transport in WIMS by the characteristics method

Creators

  • 1. U.K. Atomic Energy Authority, Dorchester (United Kingdom)

Description

The common methods of solving the neutron transport equation in reactor assembly geometries involve some geometric approximation. The standard differential transport methods and diffusion methods rely on pin-cell smearing, and transmission probability methods make approximations to the boundary fluxes linking pin cells. Integral transport methods (collision probabilities) can cope with pin geometries by numerical integration but require excessive computing times that increase with the square of the number of regions. The characteristics method in WIMS, known as CACTUS, solves the differential transport equation by a numerical tracking technique whose accuracy is limited only by computing resources; in its WIMS implementation it can handle any pin-type geometry without the need for preliminary spatial smearing

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
68
Journal Page Range
p. 454.
ISSN
0003-018X
CODEN
TANSAO

Conference

Title
American Nuclear Society (ANS) annual meeting.
Dates
20-24 Jun 1993.
Place
San Diego, CA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
25024132
Subject category
S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; MATHEMATICAL MODELS; NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; NEUTRON TRANSPORT; NEUTRON TRANSPORT THEORY; NUMERICAL SOLUTION
Descriptors DEC
NEUTRAL-PARTICLE TRANSPORT; RADIATION FLUX; RADIATION TRANSPORT; SIMULATION; TRANSPORT THEORY

Optional Information

Secondary number(s)
CONF-930601--.