Uncollided Flux Implementation for Discrete Ordinates Radiation Transport Solutions in Rattlesnake
Creators
- 1. Texas A & M University, College Station, TX (United States)
- 2. Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Description
Simulation of neutron streaming over long distances in optically thin narrow pipes sur- rounded by optically thicker materials that can absorb and/or scatter neutrons presents a simulation challenge to most neutron transport methods. Without sophisticated variance reduction techniques, this problem can be intractable for Monte Carlo techniques. Deterministic methods are often limited due to large angular discretization errors, this phenomenon is commonly known as ray effects. The uncollided component of the angular flux solution is the most anisotropic part and it can be difficult for discrete ordinate methods to accurately represent. The number of discrete angles required to overcome these ray effects is prohibitively large for the hodoscope configuration. Hence, other approaches must be taken to better simulate neutron streaming within the hodoscope collimator slots. In this report, we present an algorithm for semi-analytical calculation of the uncollided flux.
Availability note (English)
Available from https://www.osti.gov/servlets/purl/1468543; https://www.osti.gov/biblio/1468543; DOE Accepted Manuscript full text, or the publishers Best Available Version will be available free of charge after the embargo periodAdditional details
Identifiers
Publishing Information
- Imprint Pagination
- 36 p.
- Report number
- INL-EXT--17-43210-Rev000
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 53044593
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; DISCRETE ORDINATE METHOD; HODOSCOPES; MATHEMATICAL SOLUTIONS; MONTE CARLO METHOD; NEUTRON TRANSPORT
- Descriptors DEC
- CALCULATION METHODS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; SIMULATION
Optional Information
- Contract/Grant/Project number
- AC07-05ID14517
- Funding organization
- USDOE Office of Nuclear Energy - NE (United States)
- Secondary number(s)
- OSTIID--1468543