Criticality accident alarm system analysis using MCNP6.2 constructive solid geometry/unstructured mesh hybrid
Creators
- 1. Los Alamos National Laboratory, Box 1663 Mailstop A143, Los Alamos, NM 87545 (United States)
- 2. Varex Imaging, 6659 Kimball Drive Suite E502 Gig Harbor, WA 98335 (United States)
Description
Criticality Accident Alarm System (CAAS) design, analysis, and simulation require a combination of methodologies and techniques used for both criticality and shielding problems. MCNP6.2 is a general-purpose Monte Carlo radiation transport package with continuous-energy neutron and photon physics making it suitable for CAAS analysis and simulation. Use of MCNP6 for analysis of criticality accident alarm systems has typically been done by building constructive solid geometry (CSG) models that may include extensive effort spent in specification. In this work a constructive solid geometry/unstructured mesh hybrid model is created for use with MCNP6.2. The model is chosen for appropriateness to demonstrate the MCNP6 CSG/UM capability for solving problems relevant to CAAS analysis and for comparison to traditional CSG models used for analyzing criticality accident alarm systems. CAAS problems typically require the use of variance reduction techniques. Methods designed to increase the efficiency of the calculations are discussed. Deterministic variance reduction methods available in Atilla10.0 are applied to the hybrid CSG/UM model. Monte Carlo/deterministic hybrid variance reduction, in which FW-CADIS (forward-weighted consistently adjoint driven importance sampling) is used on the mesh in a deterministic calculation to generate weight windows and source biasing parameters which are applied in the MCNP6.2 simulations. Results for CAAS analysis are presented and compared for MCNP6.2 unstructured mesh, constructive solid geometry, and unstructured mesh/constructive solid geometry hybrid models. Visualization of MCNP6.2 results, including use of the MCNP6 UM elemental edit output files and FMESH tallies over the geometry under consideration is presented. (authors)
Files
Additional details
Publishing Information
- Imprint Pagination
- 10 p.
- Report number
- INIS-FR--21-0255
Conference
- Title
- ICNC 2019 - 11. international conference on nuclear criticality safety
- Dates
- 15-20 Sep 2019
- Place
- Paris (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 52015200
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALARM SYSTEMS; COMPUTERIZED SIMULATION; CRITICALITY; FUEL FABRICATION PLANTS; MESH GENERATION; RADIATION MONITORING; VALIDATION
- Descriptors DEC
- MONITORING; NUCLEAR FACILITIES; SIMULATION; TESTING
Optional Information
- Notes
- 11 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses