Development of a methodology to estimate the statistical SDR uncertainty with R2S-UNED
Creators
- 1. Departamento de Ingeniería energética, E.T.S. Ingenieros Industriales UNED, Calle Juan del Rosal 12, Madrid, 28040 (Spain)
Description
Highlights: • Scheme to calculate statistical uncertainty due to the calculation method in MC R2S. • It does not add additional assumptions to those considered in R2S calculations. • It includes the calculation of the statistical covariance matrix of the neutron flux. • Application to SDR ITER benchmark shows that covariance of neutron flux is relevant. • Guideline to improve the applicability of the scheme is proposed. The Rigorous-Two-Steps (R2S) is one of the most useful methods to estimate the Shutdown Dose Rate (SDR). The most advanced R2S tools couple neutron and photon transport, which are often simulated using Monte Carlo (MC) codes, through an activation simulation using mesh-based techniques to improve the spatial resolution of the neutron flux and the decay gamma source. One of the problems of the methodology is that the statistical uncertainty of the neutron flux due to the MC method used by the transport codes is not considered by most R2S implementations. Consequently, larger tolerance must be assumed affecting to the design of the nuclear facilities. This article describes a scheme allowing the calculation of the SDR statistical uncertainty without any additional assumptions than those used in the R2S methodology. The approach proposed in this article is suitable for cell- and mesh-based R2S implementations. In this work, the methodology was implemented in the R2S-UNED code. The accurate application of the methodology requires the full the neutron flux uncertainty (covariance matrix) as input data. MCNP was modified to calculate this matrix, although, it cannot be calculated for most of the realistic R2S simulations due to its size. If that is the situation, we propose a guideline to reduce the size of the covariance matrix to be calculated according to its element contribution to the SDR. When this guideline cannot be applied, the methodology still allows calculating the upper and lower SDR uncertainty bounds. In this article, the guideline is applied to the calculation of the SDR uncertainty in the computational benchmark of ITER. In addition, we also study the possible impact of the neutron flux correlation degree on the SDR uncertainty in this benchmark.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2021.112696Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2021.112696;
- PII
- S0920379621004725;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 168
- Journal Page Range
- vp.
- ISSN
- 0920-3796
- CODEN
- FEDEEE
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54004442
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Descriptors DEI
- BENCHMARKS; COMPUTERIZED SIMULATION; DESIGN; DOSE RATES; GAMMA SOURCES; ITER TOKAMAK; MATRICES; MONTE CARLO METHOD; NEUTRON FLUX; NEUTRONS; PHOTON TRANSPORT; RECOMMENDATIONS; SPATIAL RESOLUTION
- Descriptors DEC
- BARYONS; CALCULATION METHODS; CLOSED PLASMA DEVICES; ELEMENTARY PARTICLES; FERMIONS; HADRONS; NEUTRAL-PARTICLE TRANSPORT; NUCLEONS; RADIATION FLUX; RADIATION SOURCES; RADIATION TRANSPORT; RESOLUTION; SIMULATION; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Copyright
- Copyright (c) 2021 The Author(s). Published by Elsevier B.V.