Published March 2025 | Version v2
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Reliability-Based Optimisation with Nuclear Data Uncertainty

  • 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.

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Part of:
Topical Issues in Nuclear Installation Safety. Strengthening the Safety of Evolutionary and Innovative Reactor Designs. Proceedings of an International Conference. Supplementary Files

Additional details

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)