Published 2013 | Version v1
Book

The Serpent Monte Carlo code: status, development and applications in 2013

Description

During its nine years of development, the Serpent code has evolved from a simplified Monte Carlo lattice transport code into a versatile reactor physics calculation tool, with applications ranging from group constant generation to fuel cycle analysis, reactor modeling and coupled multi-physics calculations. The code is currently used in 100 universities and research organizations around the world, and the growing user community has taken an active role in the project. User feedback has proven an invaluable resource for code validation, as well as the development of new features and capabilities. The development of the most recent version of the code, Serpent 2, started in October 2010, and the work is still in progress. The efforts are divided between two major fields of applications: 1) Group constant generation, and 2) Coupled multi-physics calculations. Topics falling into the first category include development of deterministic diffusion solvers for the purpose of calculating assembly discontinuity factors and pin-power reconstruction for geometries homogenized without zero net-current boundary conditions, and an automated burnup sequence capable of performing branch and coefficient calculations. Work on multi-physics applications is still at a relatively early stage, and near-future topics include completing and testing the universal multi-physics interface, and the implementation of internal solvers for fuel behavior and thermal hydraulics

Availability note (English)

Available from doi: http://dx.doi.org/10.1051/snamc/201406021

Additional details

Identifiers

Publishing Information

Publisher
EDP Sciences
Imprint Place
Les Ulis (France)
Imprint Pagination
(Suppl.) 11 p.

Conference

Title
SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo
Dates
27-31 Oct 2013
Place
Paris (France)

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
46007326
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; COMPUTERIZED SIMULATION; GROUP CONSTANTS; HOMOGENIZATION METHODS; MONTE CARLO METHOD; NEUTRON TRANSPORT THEORY; S CODES
Descriptors DEC
CALCULATION METHODS; COMPUTER CODES; CROSS SECTIONS; SIMULATION; TRANSPORT THEORY

Optional Information

Notes
135 refs.