Published 2005 | Version v1
Miscellaneous

SIMULATE-4 multigroup nodal code with microscopic depletion model

  • 1. Studsvik Scandpower, Inc., Newton, MA (United States)
  • 2. Studsvik Scandpower AB, Vasteras (Sweden)
  • 3. Studsvik Scandpower, Inc., Idaho Falls, ID (United States)

Description

SIMULATE-4 is a three-dimensional multigroup analytical nodal code with microscopic depletion capability. It has been developed employing 'first principal models' thus avoiding ad hoc approximations. The multigroup diffusion equations or, optionally, the simplified P3 equations are solved. Cross sections are described by a hybrid microscopic-macroscopic model that includes approximately 50 heavy nuclides and fission products. Heterogeneities in the axial direction of an assembly are treated systematically. Radially, the assembly is divided into heterogeneous sub-meshes, thereby overcoming the shortcomings of spatially-averaged assembly cross sections and discontinuity factors generated with zero net-current boundary conditions. Numerical tests against higher order transport methods and critical experiments show substantial improvements compared to results of existing nodal models. (authors)

Availability note (English)

Available from SFEN, 5 rue des Morillons, 75015 - Paris (France)

Additional details

Publishing Information

Publisher
SFEN
Imprint Place
Paris (France)
Imprint Pagination
14 p.
Report number
INIS-FR--09-1032

Conference

Title
international topical meeting on mathematics and computation, supercomputing, reactor physics and nuclear and biological applications
Acronym
M and C 2005
Dates
12-15 Sep 2005
Place
Avignon (France)

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
40084884
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BENCHMARKS; COMPUTER CALCULATIONS; MULTIGROUP THEORY; P3-APPROXIMATION; S CODES; THREE-DIMENSIONAL CALCULATIONS; VALIDATION; WATER COOLED REACTORS
Descriptors DEC
APPROXIMATIONS; CALCULATION METHODS; COMPUTER CODES; NEUTRON TRANSPORT THEORY; REACTORS; SPHERICAL HARMONICS METHOD; TESTING; TRANSPORT THEORY

Optional Information

Notes
12 refs.