Reliability-Based Optimisation with Nuclear Data Uncertainty
Creators
- 1. Institute for Risk and Uncertainty, University of Liverpool, Liverpool (United Kingdom)
- 2. United Kingdom Atomic Energy Authority, Abingdon (United Kingdom)
- 3. Centre for Intelligent Infrastructure, University of Strathclyde, Glasgow (United Kingdom)
Description
Neutronics simulations are affected by two main sources of uncertainty: from the inherent statistical uncertainty of Monte Carlo methods employed to solve the neutron transport equation, and from nuclear data uncertainty. While the impact of the Monte Carlo statistical uncertainty on the performance and safety assessments of nuclear systems and devices is generally considered, the impact of nuclear data uncertainty is often ignored. The paper investigates whether nuclear data uncertainty is likely to have consequences on these assessments, finding that it needs to be considered in the design process of nuclear systems and devices. The paper also provides a methodology to do so in a computationally efficient way.
Files
39-47.pdf
Files
(3.1 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:4cf00c4a08dc4254c753860482736c33
|
3.1 MB | Preview Download |
Additional details
Identifiers
Publishing Information
- Imprint Place
- Vienna (International Atomic Energy Agency (IAEA))
- ISBN
- 978-92-0-103825-8
- Imprint Pagination
- 9 p.
- Series
- Proceeding Series
- ISSN
- 0074-1884
- Report number
- STI/PUB/2108
Conference
- Title
- International Conference on Topical Issues in Nuclear Installation Safety: Strengthening Safety of Evolutionary and Innovative Reactor Designs
- Dates
- 18-21 October 2022
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; EQUATIONS; MONTE CARLO METHOD; NEUTRON PHYSICS; NEUTRON TRANSPORT THEORY; NUCLEAR DATA COLLECTIONS; OPTIMIZATION; PERFORMANCE; PROBABILISTIC ESTIMATION; REACTOR KINETICS; REACTOR PHYSICS; RELIABILITY; RISK ASSESSMENT; SAFETY ANALYSIS; SIMULATION; TRANSPORT THEORY
- Descriptors DEC
- CALCULATION METHODS; KINETICS; PHYSICS; SIMULATION; TRANSPORT THEORY
Optional Information
- Notes
- 13 refs.
- Secondary number(s)
- IAEA-CN--308(SUPPLEMENTARY FILES)