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Featured researches published by Joon H. Lee.


Reliability Engineering & System Safety | 2014

Waste package degradation from thermal and chemical processes in performance assessments for the Yucca Mountain disposal system for spent nuclear fuel and high-level radioactive waste

Rob P. Rechard; Joon H. Lee; Ernest Hardin; Charles R. Bryan

Abstract This paper summarizes modeling of waste container degradation in performance assessments conducted between 1984 and 2008 to evaluate feasibility, viability, and assess compliance of a repository for spent nuclear fuel and high-level radioactive waste at Yucca Mountain, Nevada. As understanding of the Yucca Mountain disposal system increased, modeling of container degradation evolved from a component of the source term in 1984 to a separate module describing both container and drip shield degradation in 2008. A thermal module for evaluating the influence of higher heat loads from more closely packed, large waste packages was also introduced. In addition, a module for evaluating drift chemistry was added in later PAs to evaluate the potential for localized corrosion of the outer barrier of the waste container composed of Alloy 22, a highly corrosion-resistant nickel–chromium–tungsten–molybdenum alloy. The uncertainty of parameters related to container degradation contributed significantly to the estimated uncertainty of performance measures (cumulative release in assessments prior to 1995 and individual dose, thereafter).


Volume 1: Low/Intermediate-Level Radioactive Waste Management; Spent Fuel, Fissile Material, Transuranic and High-Level Radioactive Waste Management | 2013

Impact of Advanced Fuel Cycles on Uncertainty Associated with Geologic Repositories.

Rob P. Rechard; Joon H. Lee; Mark Sutton; Harris R. Greenberg; Bruce A. Robinson; W. Mark Nutt

This paper provides a qualitative evaluation of the impact of advanced fuel cycles, particularly partition and transmutation of actinides, on the uncertainty associated with geologic disposal. Based on the discussion, advanced fuel cycles, will not materially alter (1) the repository performance, (2) the spread in dose results around the mean, (3) the modeling effort to include significant features, events, and processes in the performance assessment, or (4) the characterization of uncertainty associated with a geologic disposal system in the regulatory environment of the United States.Copyright


Archive | 2011

Nuclear Energy Advanced Modeling and Simulation (NEAMS) Waste Integrated Performance and Safety Codes (IPSC): Gap Analysis for High Fidelity and Performance Assessment Code Development

Joon H. Lee; Malcolm Dean Siegel; Jose G. Arguello; Stephen Walter Webb; Thomas A. Dewers; Paul Mariner; Harold Carter Edwards; Timothy Jesse. Fuller; Geoffrey A. Freeze; Carlos F. Jove-Colon; Yifeng Wang

This report describes a gap analysis performed in the process of developing the Waste Integrated Performance and Safety Codes (IPSC) in support of the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The goal of the Waste IPSC is to develop an integrated suite of computational modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with rigorous verification, validation, and software quality requirements. The gap analyses documented in this report were are performed during an initial gap analysis to identify candidate codes and tools to support the development and integration of the Waste IPSC, and during follow-on activities that delved into more detailed assessments of the various codes that were acquired, studied, and tested. The current Waste IPSC strategy is to acquire and integrate the necessary Waste IPSC capabilities wherever feasible, and develop only those capabilities that cannot be acquired or suitably integrated, verified, or validated. The gap analysis indicates that significant capabilities may already exist in the existing THC codes although there is no single code able to fully account for all physical and chemical processes involved in a waste disposal system. Large gaps exist in modeling chemical processes and their couplings with other processes. The coupling of chemical processes with flow transport and mechanical deformation remains challenging. The data for extreme environments (e.g., for elevated temperature and high ionic strength media) that are needed for repository modeling are severely lacking. In addition, most of existing reactive transport codes were developed for non-radioactive contaminants, and they need to be adapted to account for radionuclide decay and in-growth. The accessibility to the source codes is generally limited. Because the problems of interest for the Waste IPSC are likely to result in relatively large computational models, a compact memory-usage footprint and a fast/robust solution procedure will be needed. A robust massively parallel processing (MPP) capability will also be required to provide reasonable turnaround times on the analyses that will be performed with the code. A performance assessment (PA) calculation for a waste disposal system generally requires a large number (hundreds to thousands) of model simulations to quantify the effect of model parameter uncertainties on the predicted repository performance. A set of codes for a PA calculation must be sufficiently robust and fast in terms of code execution. A PA system as a whole must be able to provide multiple alternative models for a specific set of physical/chemical processes, so that the users can choose various levels of modeling complexity based on their modeling needs. This requires PA codes, preferably, to be highly modularized. Most of the existing codes have difficulties meeting these requirements. Based on the gap analysis results, we have made the following recommendations for the code selection and code development for the NEAMS waste IPSC: (1) build fully coupled high-fidelity THCMBR codes using the existing SIERRA codes (e.g., ARIA and ADAGIO) and platform, (2) use DAKOTA to build an enhanced performance assessment system (EPAS), and build a modular code architecture and key code modules for performance assessments. The key chemical calculation modules will be built by expanding the existing CANTERA capabilities as well as by extracting useful components from other existing codes.


Archive | 2011

Granite Disposal of U.S. High-Level Radioactive Waste

Sandia Report; Paul E. Mariner; Joon H. Lee; Ernest Hardin; Geoff Freeze; Anna S. Lord; Barry Goldstein; Ron H. Price


MRS Online Proceedings Library Archive | 2011

Preliminary Performance Assessment for Deep Borehole Disposal of High-Level Radioactive Waste

Peter N. Swift; Bill Walter Arnold; Patrick V. Brady; Geoffrey A. Freeze; Teklu Hadgu; Joon H. Lee


Archive | 2010

A performance assessment model for generic repository in salt formation.

Yifeng Wang; Malcolm Dean Siegel; Peter N. Swift; Joon H. Lee; Carlos F. Jove-Colon


Archive | 2012

A prototype performance assessment model for generic deep borehole repository for high-level nuclear waste.

Joon H. Lee; Bill Walter Arnold; Peter N. Swift; Teklu Hadgu; Geoffrey A. Freeze; Yifeng Wang


Archive | 2012

A Preliminary Performance Assessment for Salt Disposal of High-Level Nuclear Waste - 12173

Joon H. Lee; Daniel James Clayton; Carlos F. Jove-Colon; Yifeng Wang


13th International High-Level Radioactive Waste Management Conference 2011, IHLRWMC 2011 | 2011

Closing the nuclear fuel cycle with salt

Yifeng Wang; Michael F. Simpson; Jonathan S. Rath; Francis D. Hansen; Joon H. Lee; Carlos F. Jove-Colon; Kevin McMahon; Peter N. Swift


Corrosion | 2003

A Probabilistic Performance Assessment Model for General Corrosion of Alloy 22 for High Level Nuclear Waste Disposal Container

Joon H. Lee; Hatem A. Elayat

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Yifeng Wang

Sandia National Laboratories

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Geoffrey A. Freeze

Sandia National Laboratories

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Peter N. Swift

Sandia National Laboratories

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Carlos F. Jove-Colon

Sandia National Laboratories

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Bill Walter Arnold

Sandia National Laboratories

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Ernest Hardin

Sandia National Laboratories

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Rob P. Rechard

Sandia National Laboratories

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Teklu Hadgu

Sandia National Laboratories

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Malcolm Dean Siegel

Sandia National Laboratories

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