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Experimental and Analytical Plans for the Non-Destructive Assay System of the Swedish Encapsulation and Repository Facilities

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TLDR
In this article, the capability of non-destructive assay (NDA) techniques to meet the combined needs of the safeguards community and the Swedish encapsulation and repository facilities operator SKB was evaluated.
Abstract
The Swedish Nuclear Fuel and Waste Management Company (SKB), European Atomic Energy Community (Euratom), two universities and several U.S. Department of Energy Laboratories have joined in a collaborative research effort to determine the capability of non-destructive assay (NDA) techniques to meet the combined needs of the safeguards community and the Swedish encapsulation and repository facilities operator SKB. These needs include partial defect detection, heat quantification, assembly identification (initial enrichment, burnup and cooling time), and Pu mass and reactivity determination. The experimental component of this research effort involves the measurement of 50 assemblies at the Central Storage of Spent Nuclear Fuel (Clab) facility in Sweden, 25 of which were irradiated in Pressurized Water Reactors and 25 in Boiling Water Reactors. The experimental signatures being measured for all assemblies include spectral resolved gammas (HPGe and LaBr3), time correlated neutrons (Differential Die-away Self Interrogation), time-varying and continuous active neutron interrogation (Differential Die-away and an approximation of Californium Interrogation Prompt Neutron), total neutron and total gamma fluxes (Fork Detector), total heat (assembly length calorimeter) and possibly the Cerenkov light emission (Digital Cerenkov Viewing Device). This paper fits into the IAEA’s Department of Safeguards Long-Term R&D Plan in the context of developing “more sensitive and less intrusive alternatives to existing NDA instruments to perform partial defect test on spent fuel assembly prior to transfer to difficult to access storage,” as well as potentially supporting pyrochemical processing. The work describes the specific measured signatures, the uniqueness of the information contained in these signatures and why a data mining approach is being used to combine the various signatures to optimally satisfy the various needs of the collaboration. This paper will address efficient and effective verification strategies particularly in the context of encapsulation and repository facilities.

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Citations
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Journal ArticleDOI

PWR and BWR spent fuel assembly gamma spectra measurements

TL;DR: In this paper, the authors focused on spectrally resolved gamma-ray measurements performed on a diverse set of 50 spent fuel assemblies [25 pressurized water reactor (PWR) assemblies and 25 boiling water Reactor (BWR), and these same 50 assemblies will be measured with neutron-based NDA instruments and a full-length calorimeter.
Journal ArticleDOI

Measuring spent fuel assembly multiplication in borated water with a passive neutron albedo reactivity instrument

TL;DR: In this article, the performance of a passive neutron albedo reactivity (PNAR) instrument to measure neutron multiplication of spent nuclear fuel in borated water is investigated as part of an integrated non-destructive assay safeguards system.
References
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Validation of new depletion capabilities and ENDF/B-VII data libraries in SCALE

TL;DR: In this paper, the authors evaluate the effect of new developments on the code performance of SCALE, a comprehensive modeling and simulation suite for nuclear safety analysis and design developed and maintained by Oak Ridge National Laboratory.
Journal ArticleDOI

Fissile and fertile nuclear material measurements using a new differential die-away self-interrogation technique

TL;DR: In this article, a new technique called differential die-away self-interrogation is presented for the measurement of fissile and fertile nuclear materials in spent fuel and plutonium-laden materials such as mixed oxide (MOX) fuel.
Book

Studies of Nuclear Fuel by Means of Nuclear Spectroscopic Methods

Peter Jansson
TL;DR: The increasing demand for characterization of nuclear fuel, both from an operator and authority point of view, motivates the development of new experimental and, preferable, non-destructive methods as discussed by the authors.
Journal ArticleDOI

Integrated Nondestructive Assay Systems to Estimate Plutonium in Spent Fuel Assemblies

TL;DR: In this article, an integrated NDA system combining active (neutron generator) and passive neutron detection and passive gamma (PG) detection is analyzed in order to estimate the amount of plutonium, verify initial enrichment, burnup, and cooling time, and detect partial defects in a spent fuel assembly (SFA).
ReportDOI

Nondestructive Assay Options for Spent Fuel Encapsulation

TL;DR: In this article, the authors describe the role that nondestructive assay (NDA) techniques and systems of NDA techniques may have in the context of an encapsulation and deep geological repository.
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