Published 2007 | Version v1
Miscellaneous

Development of ITER 3D neutronics model and nuclear analyses

  • 1. Institute of Plasma Phsyics, Chinese Academy of Sciences, Hefei (China)

Description

ITER nuclear analyses rely on the calculations with the three-dimensional (3D) Monte Carlo code e.g. the widely-used MCNP. However, continuous changes in the design of the components require the 3D neutronics model for nuclear analyses should be updated. Nevertheless, the modeling of a complex geometry with MCNP by hand is a very time-consuming task. It is an efficient way to develop CAD-based interface code for automatic conversion from CAD models to MCNP input files. Based on the latest CAD model and the available interface codes, the two approaches of updating 3D nuetronics model have been discussed by ITER IT (International Team): The first is to start with the existing MCNP model 'Brand' and update it through a combination of direct modification of the MCNP input file and generation of models for some components directly from the CAD data; The second is to start from the full CAD model, make the necessary simplifications, and generate the MCNP model by one of the interface codes. MCAM as an advanced CAD-based MCNP interface code developed by FDS Team in China has been successfully applied to update the ITER 3D neutronics model by adopting the above two approaches. The Brand model has been updated to generate portions of the geometry based on the newest CAD model by MCAM. MCAM has also successfully performed conversion to MCNP neutronics model from a full ITER CAD model which is simplified and issued by ITER IT to benchmark the above interface codes. Based on the two updated 3D neutronics models, the related nuclear analyses are performed. This paper presents the status of ITER 3D modeling by using MCAM and its nuclear analyses, as well as a brief introduction of advanced version of MCAM. (authors)

Part of:
Ninth China-Japan symposium on materials for advanced energy systems and fission and fusion engineering jointed with CAS-JSPS core-university program seminar on fusion materials, system and design integration book of abstracts

Additional details

Publishing Information

Imprint Title
Ninth China-Japan symposium on materials for advanced energy systems and fission and fusion engineering jointed with CAS-JSPS core-university program seminar on fusion materials, system and design integration book of abstracts
Imprint Pagination
117 p.
Journal Page Range
p. 86

Conference

Title
9. China-Japan symposium on materials for advanced energy systems and fission and fusion engineering jointed with CAS-JSPS core-university program seminar on fusion materials, system and design integration
Dates
23-26 Oct 2007
Place
Guilin (China)

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
44042191
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BENCHMARKS; CHINA; COMPUTERIZED SIMULATION; DESIGN; GEOMETRY; ITER TOKAMAK; M CODES; MODIFICATIONS; MONTE CARLO METHOD; THREE-DIMENSIONAL CALCULATIONS
Descriptors DEC
ASIA; CALCULATION METHODS; CLOSED PLASMA DEVICES; COMPUTER CODES; MATHEMATICS; SIMULATION; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Collaborations
FDS team