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Journal ArticleDOI

Next Generation Safeguards Initiative research to determine the Pu mass in spent fuel assemblies: Purpose, approach, constraints, implementation, and calibration

TLDR
The Next Generation Safeguards Initiative (NGSI) as mentioned in this paper developed a Monte Carlo model to quantify the plutonium mass in spent nuclear fuel assemblies and to detect the diversion of pins from them.
Abstract
The Next Generation Safeguards Initiative (NGSI) of the U.S. Department of Energy has funded a multi-lab/multi-university collaboration to quantify the plutonium mass in spent nuclear fuel assemblies and to detect the diversion of pins from them. The goal of this research effort is to quantify the capability of various non-destructive assay (NDA) technologies as well as to train a future generation of safeguards practitioners. This research is “technology driven” in the sense that we will quantify the capabilities of a wide range of safeguards technologies of interest to regulators and policy makers; a key benefit to this approach is that the techniques are being tested in a unified manner. When the results of the Monte Carlo modeling are evaluated and integrated, practical constraints are part of defining the potential context in which a given technology might be applied. This paper organizes the commercial spent fuel safeguard needs into four facility types in order to identify any constraints on the NDA system design. These four facility types are the following: future reprocessing plants, current reprocessing plants, once-through spent fuel repositories, and any other sites that store individual spent fuel assemblies (reactor sites are the most common facility type in this category). Dry storage is not of interest since individual assemblies are not accessible. This paper will overview the purpose and approach of the NGSI spent fuel effort and describe the constraints inherent in commercial fuel facilities. It will conclude by discussing implementation and calibration of measurement systems. This report will also provide some motivation for considering a couple of other safeguards concepts (base measurement and fingerprinting) that might meet the safeguards need but not require the determination of plutonium mass.

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Citations
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Journal ArticleDOI

Rattling nucleons: New developments in active interrogation of special nuclear material

TL;DR: Active interrogation is a vigorous area of research and development due to its promise of offering detection and characterization capabilities of special nuclear material in environments where passive detection fails as mentioned in this paper, and advocates hope that active interrogation will provide a solution to the problem of detecting shielded uranium.
Journal ArticleDOI

EJ-309 pulse shape discrimination performance with a high gamma-ray-to-neutron ratio and low threshold

TL;DR: In this paper, the EJ-309 scintillator was used to measure neutrons in the presence of high gamma-ray fluence, which is a challenge with multi-particle detectors.

Development of Self-Interrogation Neutron Resonance Densitometry (SINRD) to Measure the Fissile Content in Nuclear Fuel

TL;DR: In this article, LaFleur et al. developed Self-Interrogation Neutron Resonance Densitometry (SINRD) to measure the fissile content in nuclear fuel.
Journal ArticleDOI

Application of Laser Compton Scattered gamma-ray beams to nondestructive detection and assay of nuclear material

TL;DR: In this article, a high-brightness gamma-ray source based on modern laser and accelerator technologies is proposed for non-destructive detection and assay of nuclides, which are necessary for nuclear security and safeguards.
ReportDOI

Neutron Resonance Transmission Analysis (NRTA): A Nondestructive Assay Technique for the Next Generation Safeguards Initiative’s Plutonium Assay Challenge

TL;DR: The Neutron Resonance Transmission Analysis (NRTA) technique was used in the first year of the Plutonium Assay Challenge (NA-241) as discussed by the authors, which was funded by the National Nuclear Security Administration's Office of Nuclear Safeguards.
References
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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.
ReportDOI

Development of Monteburns: A Code That Links MCNP and ORIGEN2 in an Automated Fashion for Burnup Calculations

TL;DR: The monteburns code, designed for use in the Accelerator Transmutation of Waste project at Los Alamos National Laboratory but also being applied to the analysis of isotopic production/destruction of transuranic actinides in a reactor system, has now been shown to sufficiently support these calculations.
Journal ArticleDOI

Calling for action

TL;DR: The Next Generation Safeguards Initiative (NGSI) as discussed by the authors aims to ensure the IAEA makes the fullest possible use of its existing authority to prevent the diversion of safeguarded material and to investigate suspicious activities.