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Title: Safegaurds Performance Modeling: New Approaches for Safeguards By Design.


Abstract not provided.

Publication Date:
Research Org.:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE), Fuel Cycle Technologies (NE-5)
OSTI Identifier:
Report Number(s):
DOE Contract Number:
Resource Type:
Resource Relation:
Conference: Proposed for presentation at the INMM Annual Meeting held July 24-28, 2016 in Atlanta, GA.
Country of Publication:
United States

Citation Formats

Cipiti, Benjamin B. Safegaurds Performance Modeling: New Approaches for Safeguards By Design.. United States: N. p., 2016. Web.
Cipiti, Benjamin B. Safegaurds Performance Modeling: New Approaches for Safeguards By Design.. United States.
Cipiti, Benjamin B. 2016. "Safegaurds Performance Modeling: New Approaches for Safeguards By Design.". United States. doi:.
title = {Safegaurds Performance Modeling: New Approaches for Safeguards By Design.},
author = {Cipiti, Benjamin B.},
abstractNote = {Abstract not provided.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 2016,
month = 8

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  • The design of the Pebble Bed Modular Reactor (PBMR) does not fit or seem appropriate to the IAEA safeguards approach under the categories of light water reactor (LWR), on-load refueled reactor (OLR, i.e. CANDU), or Other (prismatic HTGR) because the fuel is in a bulk form, rather than discrete items. Because the nuclear fuel is a collection of nuclear material inserted in tennis-ball sized spheres containing structural and moderating material and a PBMR core will contain a bulk load on the order of 500,000 spheres, it could be classified as a 'Bulk-Fuel Reactor.' Hence, the IAEA should develop unique safeguardsmore » criteria. In a multi-lab DOE study, it was found that an optimized blend of: (i) developing techniques to verify the plutonium content in spent fuel pebbles, (ii) improving burn-up computer codes for PBMR spent fuel to provide better understanding of the core and spent fuel makeup, and (iii) utilizing bulk verification techniques for PBMR spent fuel storage bins should be combined with the historic IAEA and South African approaches of containment and surveillance to verify and maintain continuity of knowledge of PBMR fuel. For all of these techniques to work the design of the reactor will need to accommodate safeguards and material accountancy measures to a far greater extent than has thus far been the case. The implementation of Safeguards-by-Design as the PBMR design progresses provides an approach to meets these safeguards and accountancy needs.« less
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  • For two decades, extensive hydrologic investigations have been conducted for geologic disposal of high-level radioactive waste in fractured volcanic tuffs at Yucca Mountain, Nevada. Extensive field and laboratory geologic, hydrologic, and geochemical testing has provided a large amount of data for developing the conceptual understanding of these processes and parameters for quantifying these processes. A suite of sophisticated numerical models has been developed to assess the long-term performance of the natural barrier of unsaturated zone (UZ) and saturated zone (SZ) to flow of groundwater and transport of radionuclides released from the repository. This work focuses on characterizing surface and subsurfacemore » processes of climate change, infiltration, percolation in the UZ and groundwater flow in the SZ, as well as on predicting hydrologic responses of the natural system to the emplacement of waste packages in drifts, including seepage of water into emplacement drifts and radionuclide transport in the UZ and SZ. These models are then abstracted into a total system performance assessment (TSPA) model. The TSPA integrates these natural attributes with features of engineered systems, and through systematic stochastic analyses involving Monte Carlo simulations, predicts the dose consequences and groundwater concentrations for at least 10,000 years for various future climate conditions, waste types, release scenarios, and transport pathways. The TSPA predictions demonstrate compliance with postclosure individual and groundwater protection standards in the license application for the repository. This presentation provides an overview of the development and use of these natural-system models, including the infiltration model, the site-scale UZ flow model, the seepage calibration and abstraction models, the UZ radionuclide transport and abstraction models, and the site-scale SZ flow and transport models. It describes the approaches used in the design and construct of these models, summarizes the tests and experiments conducted to obtain key input data, and discusses lessons learned in the efforts to validate the models and the treatment of uncertainties in the TSPA.« less