Published August 2003 | Version v1
Report Metadata-only

Computation of selected parameters of WWER-1000 fuel assembly by HELIOS and MCNP codes

Creators

Description

HELIOS is a code serving to calculate nuclear fuel burn-up. It is designed to provide numerical solution both of the problem of criticality for the neutron transport equation and of equations of point kinetics. To achieve reasonably short running times, certain simplifications are introduced into the code. The question was addressed as to how those simplifications affect the accuracy of the calculated burn-up. To this purpose, we applied the HELIOS code to solve the problem of criticality for neutron transport for the WWER-1000 fuel assembly. The calculations were performed for several variants of the assembly and the results obtained were compared with those obtained by using the MCNP code

Availability note (English)

Available (also in the electronic format as a PDF reproduction) from Nuclear Research Institute Rez, 250 68 Rez, Czech Republic; e-mail contact: ret@nri.cz

Additional details

Publishing Information

Imprint Pagination
[36 p.]
Report number
UJV--11933-R

INIS

Country of Publication
Czech Republic
Country of Input or Organization
Czech Republic
INIS RN
38005997
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
ACCURACY; BURNUP; COMPUTER CALCULATIONS; CRITICALITY; FUEL ASSEMBLIES; H CODES; M CODES; MATHEMATICAL MODELS; NEUTRON TRANSPORT; NUMERICAL SOLUTION; WWER TYPE REACTORS
Descriptors DEC
COMPUTER CODES; ENRICHED URANIUM REACTORS; MATHEMATICAL SOLUTIONS; NEUTRAL-PARTICLE TRANSPORT; POWER REACTORS; PWR TYPE REACTORS; RADIATION TRANSPORT; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
15 tabs., 3 figs., 2 refs.