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.czAdditional 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.