Published 2022 | Version v1
Miscellaneous

Analysis of a Generic Hot Cell Facility Using Attila and MCNP - 22178

  • 1. Silver Fir Software, Inc. (United States)
  • 2. Kinectrics Inc. (Canada)

Description

This paper is a collaboration between Kinectrics and Silver Fir Software. Kinectrics provides a variety of engineering services to the Canadian nuclear industry, including radiation shielding assessments, dose rate field analyses, and environment and health physics. Silver Fir Software develops software to simplify radiation shielding analyses. Silver Fir's flagship software product is Attila, a computer aided design (CAD) integrated radiation transport suite including a graphical user interface (GUI) front end, the Attila deterministic solver, and a graphical user interface (GUI) pre/post processor (Attila4MC) for the MCNP Monte Carlo solver, the nuclear industry standard Monte Carlo code. This paper is intended to demonstrate the utility of the Attila workflow for use in waste management applications, which include generation of three-dimensional dose rate maps to aid in dose planning, human factors, waste routes and storage optimization, etc. This is demonstrated through a case study of a generic hot cell facility. A generic hot cell facility was constructed in CAD and imported into the Attila GUI for analysis with both MCNP and the deterministic Attila solver. The Attila solver is a three-dimensional discrete ordinance (SN) particle transport code that solves the Linear Boltzmann Transport Equation on an unstructured tetrahedral mesh. Using Attila in the Attila4MC mode, the MCNP calculation input files are also generated from the same CAD model. Attila4MC also supports weight windows variance reduction using the CADIS and FW-CADIS methods, where weight windows are automatically generated by the Attila solver. Dose field solutions from both methods are visualized and compared. Use of single workflow to generate both the Attila Deterministic Solver and Attila4MC solutions in this case study demonstrates the utility of creating calculation-method independent cross-checks for radiation transport problems (deterministic vs Monte Carlo). (authors)

Availability note (English)

Available from: WM Symposia, Inc., PO Box 27646, 85285-7646 Tempe, AZ (US)

Additional details

Publishing Information

Imprint Pagination
8 p.
Report number
INIS-US--24-WM-22178

Conference

Title
WM2022 - 48. Annual Waste Management Conference
Dates
6-10 Mar 2022
Place
Phoenix - Arizona (United States)

Optional Information

Notes
6 refs.; available online at: https://www.xcdsystem.com/wmsym/2022/sessions.cfm