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Uncertainties in transport theory pressure vessel neutron fluence calculations

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TLDR
In this article, the authors use particle transport theory methods and analysis to estimate the neutron and/or gamma fluence distributions of the pressure vessel in PWRs and vessel internals in boiling water reactors.
Abstract
The desire for increasing safety margins (increased power production and plant availability), the fact that many existing plants are approaching the final years of their design lifetime, and the consideration of life extension have resulted in the need for performing more accurate estimation of parameters that affect plant performance and safety. This means that more accurate calculational and experimental methodologies for estimating the neutron and/or gamma fluence distributions are needed to ensure the structural integrity of the pressure vessel in pressurized water reactors (PWRs) and vessel internals in boiling water reactors. Such an estimation requires the use of particle transport theory methods and analysis; because of the existing uncertainties in the input parameters and numerical methods, it is necessary to estimate the uncertainties in the calculated results.

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Journal ArticleDOI

Multidimensional deterministic nuclear data sensitivity and uncertainty code system : Method and application

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Development of the CPXSD Methodology for Generation of Fine-Group Libraries for Shielding Applications

TL;DR: In this paper, the authors have developed the Contributon and Point-wise Cross Section Driven (CPXSD) methodology for constructing effective fine and broad-group cross-section structures.
Dissertation

Uncertainty quantification of the fast flux calculation for a PWR vessel

Laura Clouvel
TL;DR: This thesis consists in performing a new uncertainty assessment of the fast flux calculation for the PWR vessel considering the data of recent international nuclear libraries and shows the importance to consider the covariance matrices to propagate the input uncertainties, and to analyze the contribution of each input on a physical model.
Journal ArticleDOI

A new uncertainty arising in reactor pressure vessel fluence calculation

TL;DR: In this paper, a discrepancy of the RPV fast neutron fluence between heterogeneous and homogeneous assembly models, Kori Unit 1 cycle 1 core was modeled on three-dimensional representations by MCNP4A.
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