Investigations into Alternative Radiation Transport Codes for ITER Neutronics Analysis

Investigations into Alternative Radiation Transport Codes for ITER Neutronics Analysis

Investigations into Alternative Radiation Transport Codes for ITER Neutronics Analysis 150 150 UKAEA Opendata
CCFE-PR(17)10

Investigations into Alternative Radiation Transport Codes for ITER Neutronics Analysis

As radiation transport models for ITER become increasingly complex, the use of traditional constructive solid geometry (CSG) modelling approaches such as MCNP presents significant disadvantages during model creation and integration. Studies were performed to assess the capabilities of alternative mesh-based neutronics workflows offered by the MCNP [1], DAG-MCNP [2] and Serpent-2 [3] codes.

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2017 ANS Annual Meeting, San Francisco, USA, 11-15 June 2017