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Sato, Satoshi; Ochiai, Kentaro; Konno, Chikara; Morota, Hidetsugu*; Nasif, H.*; Tanaka, Masanobu*; Polunovskiy, E.*; Loughlin, M.*
Proceedings of 24th IAEA Fusion Energy Conference (FEC 2012) (CD-ROM), 8 Pages, 2013/03
Detailed nuclear analyses for the latest ITER NB system are required to ensure that NB design conforms to the nuclear regulations for the ITER building and licensing. A variety of nuclear analyses was started for ITER NB system including a tokamak building of 50m 
35m 20m and outside the building by using a Monte Carlo code MCNP in 2009. MCNP geometry input data were successfully produced from simplified NB CAD data with the improved GEOMIT code, which automatically converts CAD data to MCNP geometry input data. We have performed calculations of the effective dose rates during DT operation and after shutdown, and activation of the NB components, etc.
Fischer, U.*; Iida, Hiromasa; Li, Y.*; Loughlin, M.*; Sato, Satoshi; Serikov, A.*; Tsige-Tamirat, H.*; Tautges, T.*; Wilson, P. P.*; Wu, Y.*
Fusion Science and Technology, 56(2), p.702 - 709, 2009/08
Times Cited Count：13 Percentile：62.36(Nuclear Science & Technology)Several approaches have been recently developed to make available CAD geometry data for Monte Carlo calculations with the MCNP code. Among these are conversion tools for the automatic generation of geometry models in MCNP representation such as MCAM of China, McCad of Germany, and GEOMIT of JAEA, as well as the direct DAG-MCNPX approach developed by USA. An extensive benchmark exercise has been conducted on ITER between 2005 and 2007 with the objective to test and validate the different approaches and thereby check the maturity level for ITER design applications. The exercise encompassed the generation of a dedicated neutronics CATIA model based on available engineering CAD design data, the conversion into MCNP geometry, the verification of the converted models, and a number of calculations to compare the different approaches with regard to the performance and the validity of the results obtained. The paper briefly reviews the different approaches and provides a detailed description of the ITER benchmark effort, its results and conclusions. As a key issue, the recommendations are discussed that need to be followed when generating a neutronics CAD model for ITER design calculations. This is considered essential since the ITER quality assurance requirements will request the consistency of the analysis models and the underlying engineering CAD models.
Loughlin, M. J.*; Batistoni, P.*; Konno, Chikara; Fischer, U.*; Iida, Hiromasa; Petrizzi, L.*; Polunovskiy, E.*; Sawan, M.*; Wilson, P.*; Wu, Y.*
Fusion Science and Technology, 56(2), p.566 - 572, 2009/08
Times Cited Count：42 Percentile：92.56(Nuclear Science & Technology)It is envisaged that ITER should produce as much as 700 MW of fusion power. This equates to the production of 2.4810
14MeV neutrons/s which will give an uncollided flux at the first wall of approximately 410
n/cm
/s and a total with the addition of the collided to some 10
n/cm/s. ITER is therefore a significant nuclear facility and it is essential that an efficient and coherent strategy for nuclear analysis is in place. This paper reviews the status of the methods applied to date and recommends the future strategy which ITER should adopt to address the continuing requirements and responsibilities. This is done by consideration of the application of radiation transport codes, the creation of suitable models, developments in information technology, and the management tools which will be required. Areas in which new codes and techniques need to be developed will be identified.
Barnes, C. W.*; Loughlin, M. J.*; Nishitani, Takeo
Review of Scientific Instruments, 68(1), p.577 - 580, 1997/01
Times Cited Count：26 Percentile：82.92(Instruments & Instrumentation)no abstracts in English
