Abstract

As in other nuclear countries, the operation of the Ignalina nuclear power plant in Lithuania has led to the accumulation of around 22 thousand assemblies of spent nuclear fuel (SNF). The development of geological disposal program involves an iterative assessment of the system safety supported by scientific research on radionuclides migration and related processes. This study focused on the application of Contribution to the Sample Mean (CSM) and Contribution to Sample Variance (CSV) methods to complement the uncertainty and sensitivity analyses of the time-dependent flux of I-129 from the engineered barriers of a conceptual disposal facility for RBMK-1500 SNF (RBMK is abbreviation of “High Power Channel-type Reactor” (in Russian)). The analysis was performed using a MATLAB platform (8.0.0.783 (R2012b), MathWorks, MA, USA). The mean and variance ratios derived from CSM and CSV plots were applied to estimate the effect of reduced uncertainty range on mean flux and its variance, and the uncertainty analysis was also complimented. Increasing the lower bounding value of defect size enlargement time range to 4.6 × 104 years would lead to a lower mean flux until 5 × 104 years after repository closure. Later on (up to 1 million years after repository closure), the only reduction of the upper bounding value of the SNF dissolution rate range would affect a decreased mean flux.

Highlights

  • As in other nuclear countries, the operation of the Ignalina nuclear power plant in Lithuania has led to the accumulation of around 22 thousand assemblies of spent nuclear fuel (SNF)

  • The parameters SNF matrix dissolution rate (SNF DR) and instant release fraction (IRF) led to the lower mean flux by decreasing the upper bound of their value range

  • −7 1/year) would lead to a decrease in the mean flux by at values

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Summary

Introduction

As in other nuclear countries, the operation of the Ignalina nuclear power plant in Lithuania has led to the accumulation of around 22 thousand assemblies of spent nuclear fuel (SNF). Based on derived CSM and CSV plots, the ranking of parameter importance was established for the time-dependent flux of I-129 through the engineered barriers of a conceptual geological repository for RBMK-1500 SNF disposal. It applied CSM- and CSV-based measures to explore the effect of parameter uncertainty reduction. The derivation of complemental results regarding importance ranking was done, where the regression-based method was unreliable, and indications about the effect of newly justified input parameter uncertainty range on the model output were available at no additional computational cost

Radionuclide Transport Model for RBMK-1500 SNF Disposal
Disposal System
Characterization of Model Behavior
Revised Mean and Variance Ratio Functions
Results and Discussion
CSM and CSV Plots for I-129 Flux
Effect of Parameter Range Reduction on Mean and Variance of I-129 flux
Variance
Effect
ForIRF the would current lead set ofto the
Conclusions

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