Published May 2012 | Version v1
Report

On solution to the problem of criticality

Description

The problem of criticality for the neutron transport equation was treated. The problem was examined in Lebesgue space L∞ and was based on some basic assumptions, which are sufficiently general and are in agreement with the spatial behaviour of both temperature and atomic densities of the materials as well as with the properties of all known models of neutron reactions with the medium. The criticality problem was transformed to one of determining the time-asymptotic behaviour of the solution with an initial condition. The initial-value problem was solved numerically by the Monte Carlo method, for which a specific random process and a random variable were constructed

Availability note (English)

Available (also in electronic format as PDF facsimile) from Nuclear Research Institute Rez, 250 68 Rez, Czech Republic; e-mail contact: lucie.richterova@ujv.cz

Additional details

Publishing Information

Imprint Pagination
18 p.
Report number
UJV--13982-RF

INIS

Country of Publication
Czech Republic
Country of Input or Organization
Czech Republic
INIS RN
45105193
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
BOUNDARY CONDITIONS; CRITICALITY; DENSITY; EQUATIONS; MATHEMATICAL OPERATORS; MONTE CARLO METHOD
Descriptors DEC
CALCULATION METHODS; PHYSICAL PROPERTIES

Optional Information

Notes
9 refs.