Development of ITER 3D neutronics model and nuclear analyses
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)
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