The use of cad based radiation transport in support of SNS: DAG-MCNP6 validation

Andrew Davis; Lucas J. Jacobson; Paul P.H. Wilson; Franz Gallmeier

The use of cad based radiation transport in support of SNS: DAG-MCNP6 validation

Andrew Davis, Lucas J. Jacobson, Paul P.H. Wilson, Franz Gallmeier

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

3 Scopus citations

Abstract

The Spallation Neutron Source (SNS) facility at Oak Ridge is the world's highest strength pulsed neutron beam facility. The design and operation of the facility depends upon the accurate simulation of the proton induced reactions in the beam target and much deeper into the device. Historically MCNP/X was the main Monte Carlo (MC) simulation package used, hence relying on the traditional Combinatorial Solid Geometry (CSG) package within. There are efforts to begin design simulations of the Second Target Station (STS) integrating with multi domain physics modelling from the start. The DAGMC (Direct Accelerated Geometry Monte Carlo) software library has been integrated with the MCNP6 package to form DAG-MCNP6, a version of MCNP6 that can transport particles through CAD geometries. This paper will focus on the discussion of the development of DAG-MCNP6 and the recent benchmarking activities using the SNS.

Original language	English
Title of host publication	13th International Topical Meeting on Nuclear Applications of Accelerators 2017, AccApp 2017
Subtitle of host publication	The Expanding Universe of Accelerator Applications
Publisher	American Nuclear Society
Pages	72-80
Number of pages	9
ISBN (Electronic)	9781510852198
State	Published - 2018
Externally published	Yes
Event	13th International Topical Meeting on Nuclear Applications of Accelerators 2017: The Expanding Universe of Accelerator Applications, AccApp 2017 - Quebec City, Canada Duration: Jul 31 2017 → Aug 4 2017

Publication series

Name	13th International Topical Meeting on Nuclear Applications of Accelerators 2017, AccApp 2017: The Expanding Universe of Accelerator Applications

Conference

Conference	13th International Topical Meeting on Nuclear Applications of Accelerators 2017: The Expanding Universe of Accelerator Applications, AccApp 2017
Country/Territory	Canada
City	Quebec City
Period	07/31/17 → 08/4/17

Funding

This work was funded, in part, by support from the U.S. Department of Energy via the Spallation Neutron Source/UT-Battelle (Project 4000149392).

Keywords

Accelerator
CAD
Monte Carlo
Neutronics
Proton

Cite this

Davis, A., Jacobson, L. J., Wilson, P. P. H., & Gallmeier, F. (2018). The use of cad based radiation transport in support of SNS: DAG-MCNP6 validation. In 13th International Topical Meeting on Nuclear Applications of Accelerators 2017, AccApp 2017: The Expanding Universe of Accelerator Applications (pp. 72-80). (13th International Topical Meeting on Nuclear Applications of Accelerators 2017, AccApp 2017: The Expanding Universe of Accelerator Applications). American Nuclear Society.

Davis, Andrew ; Jacobson, Lucas J. ; Wilson, Paul P.H. et al. / The use of cad based radiation transport in support of SNS : DAG-MCNP6 validation. 13th International Topical Meeting on Nuclear Applications of Accelerators 2017, AccApp 2017: The Expanding Universe of Accelerator Applications. American Nuclear Society, 2018. pp. 72-80 (13th International Topical Meeting on Nuclear Applications of Accelerators 2017, AccApp 2017: The Expanding Universe of Accelerator Applications).

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title = "The use of cad based radiation transport in support of SNS: DAG-MCNP6 validation",

abstract = "The Spallation Neutron Source (SNS) facility at Oak Ridge is the world's highest strength pulsed neutron beam facility. The design and operation of the facility depends upon the accurate simulation of the proton induced reactions in the beam target and much deeper into the device. Historically MCNP/X was the main Monte Carlo (MC) simulation package used, hence relying on the traditional Combinatorial Solid Geometry (CSG) package within. There are efforts to begin design simulations of the Second Target Station (STS) integrating with multi domain physics modelling from the start. The DAGMC (Direct Accelerated Geometry Monte Carlo) software library has been integrated with the MCNP6 package to form DAG-MCNP6, a version of MCNP6 that can transport particles through CAD geometries. This paper will focus on the discussion of the development of DAG-MCNP6 and the recent benchmarking activities using the SNS.",

keywords = "Accelerator, CAD, Monte Carlo, Neutronics, Proton",

author = "Andrew Davis and Jacobson, {Lucas J.} and Wilson, {Paul P.H.} and Franz Gallmeier",

note = "Publisher Copyright: Copyright{\textcopyright} (2017) by American Nuclear Society. All rights reserved.; 13th International Topical Meeting on Nuclear Applications of Accelerators 2017: The Expanding Universe of Accelerator Applications, AccApp 2017 ; Conference date: 31-07-2017 Through 04-08-2017",

year = "2018",

language = "English",

series = "13th International Topical Meeting on Nuclear Applications of Accelerators 2017, AccApp 2017: The Expanding Universe of Accelerator Applications",

publisher = "American Nuclear Society",

pages = "72--80",

booktitle = "13th International Topical Meeting on Nuclear Applications of Accelerators 2017, AccApp 2017",

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Davis, A, Jacobson, LJ, Wilson, PPH & Gallmeier, F 2018, The use of cad based radiation transport in support of SNS: DAG-MCNP6 validation. in 13th International Topical Meeting on Nuclear Applications of Accelerators 2017, AccApp 2017: The Expanding Universe of Accelerator Applications. 13th International Topical Meeting on Nuclear Applications of Accelerators 2017, AccApp 2017: The Expanding Universe of Accelerator Applications, American Nuclear Society, pp. 72-80, 13th International Topical Meeting on Nuclear Applications of Accelerators 2017: The Expanding Universe of Accelerator Applications, AccApp 2017, Quebec City, Canada, 07/31/17.

The use of cad based radiation transport in support of SNS: DAG-MCNP6 validation. / Davis, Andrew; Jacobson, Lucas J.; Wilson, Paul P.H. et al.
13th International Topical Meeting on Nuclear Applications of Accelerators 2017, AccApp 2017: The Expanding Universe of Accelerator Applications. American Nuclear Society, 2018. p. 72-80 (13th International Topical Meeting on Nuclear Applications of Accelerators 2017, AccApp 2017: The Expanding Universe of Accelerator Applications).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

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AB - The Spallation Neutron Source (SNS) facility at Oak Ridge is the world's highest strength pulsed neutron beam facility. The design and operation of the facility depends upon the accurate simulation of the proton induced reactions in the beam target and much deeper into the device. Historically MCNP/X was the main Monte Carlo (MC) simulation package used, hence relying on the traditional Combinatorial Solid Geometry (CSG) package within. There are efforts to begin design simulations of the Second Target Station (STS) integrating with multi domain physics modelling from the start. The DAGMC (Direct Accelerated Geometry Monte Carlo) software library has been integrated with the MCNP6 package to form DAG-MCNP6, a version of MCNP6 that can transport particles through CAD geometries. This paper will focus on the discussion of the development of DAG-MCNP6 and the recent benchmarking activities using the SNS.

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KW - CAD

KW - Monte Carlo

KW - Neutronics

KW - Proton

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Davis A, Jacobson LJ, Wilson PPH, Gallmeier F. The use of cad based radiation transport in support of SNS: DAG-MCNP6 validation. In 13th International Topical Meeting on Nuclear Applications of Accelerators 2017, AccApp 2017: The Expanding Universe of Accelerator Applications. American Nuclear Society. 2018. p. 72-80. (13th International Topical Meeting on Nuclear Applications of Accelerators 2017, AccApp 2017: The Expanding Universe of Accelerator Applications).

The use of cad based radiation transport in support of SNS: DAG-MCNP6 validation

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