Analysis of a Generic Hot Cell Facility Using Attila and MCNP - 22178
Creators
- 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
Identifiers
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)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 55069580
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CANADA; COMPUTER CODES; DOSE RATES; GRAPHICAL USER INTERFACE; HOT CELLS; HUMAN FACTORS; MAPS; MONTE CARLO METHOD; NUCLEAR INDUSTRY; OPTIMIZATION; RADIATION DOSES; RADIATION PROTECTION; RADIOACTIVE WASTE MANAGEMENT; SHIELDING; SILVER; TRANSPORT THEORY
- Descriptors DEC
- CALCULATION METHODS; DEVELOPED COUNTRIES; DOSES; ELEMENTS; EQUIPMENT; INDUSTRY; LABORATORY EQUIPMENT; MANAGEMENT; METALS; NORTH AMERICA; TRANSITION ELEMENTS; WASTE MANAGEMENT
Optional Information
- Notes
- 6 refs.; available online at: https://www.xcdsystem.com/wmsym/2022/sessions.cfm