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

Menlove, H.O.; Menlove, S.H.; Tobin, Stephen J

doi:10.1016/j.nima.2009.01.157

Cited by 28 publications

(46 citation statements)

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“…In line with the above, the suggestion of new Safeguards technique for MOX/spent fuel assay [26], the Differential Die-away Self-Interrogation (DDSI) technique, displayed the interest towards the energy-dependent aspects of neutron counting. In connection with this, the two-group Feynman-alpha theory was elaborated in [27] where delayed neutrons were neglected, and in [28] with inclusion of delayed neutron precursors.…”

Section: Introductionmentioning

confidence: 77%

A general analytical solution for the variance-to-mean Feynman-alpha formulas for a two-group two-point, a two-group one-point and a one-group two-point cases

Chernikova¹,

Ziguan²,

Pázsit³

et al. 2014

Eur. Phys. J. Plus

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This paper presents a full derivation of the varianceto-mean or Feynman-alpha formula in a two energy groupand two spatial region-treatment. The derivation is based on the Chapman -Kolmogorov equation with the inclusion of all possible neutron reactions and passage intensities between the two regions. In addition, the two-group one-region and the two-region one-group Feynman-alpha formulas, treated earlier in the literature for special cases, are extended for further types and positions of detectors. We focus on the possibility of using these theories for accelerator-driven systems and applications in the safeguards domain, such as the differential self-interrogation method and the differential dieaway method. This is due to the fact that the predictions from the models which are currently used do not fully describe all the effects in the heavily reflected fast or thermal systems. Therefore, in conclusion a comparative study of the two-group two-region, the two-group one-region, the onegroup two-region and the one-group one-region Feynmanalpha models is discussed.

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Section: Introductionmentioning

confidence: 77%

A general analytical solution for the variance-to-mean Feynman-alpha formulas for a two-group two-point, a two-group one-point and a one-group two-point cases

Chernikova¹,

Ziguan²,

Pázsit³

et al. 2014

Eur. Phys. J. Plus

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“…Currently, a simulation-based study utilizing a common library of spent fuel assemblies is comparing the predicted performance of various candidate NDA methods for the direct measurement of plutonium in pressurized water reactor assemblies, the most common assembly type in the world's fuel inventory [4]. Among the methods being studied are the two described above as well as differential die-away and neutron albedo interrogation (in which the fuel's neutron emissions are reflected to serve as an interrogating neutron source) [5], delayed gamma-ray spectroscopy [6], [7] and the method described in this paper, lead slowing-down spectroscopy.…”

Section: Time-spectral Analysis Methods For Spent Fuel Assay Using Lementioning

confidence: 99%

“…The challenge, then, is to formulate an analytical that accounts for self-shielding so that the masses of fissile U-235, Pu-239, and Pu-241 can be accurately calculated using (5). The Pu-240 and U-238 features in Fig.…”

Section: Time-spectra Analysis Methodsmentioning

confidence: 99%

Time-Spectral Analysis Methods for Spent Fuel Assay Using Lead Slowing-Down Spectroscopy

Smith

Anderson

Ressler

et al. 2010

IEEE Trans. Nucl. Sci.

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Nondestructive techniques for measuring the mass of fissile isotopes in spent nuclear fuel is a considerable challenge in the safeguarding of nuclear fuel cycles. A nondestructive assay technology that could provide direct measurement of fissile mass, particularly for the plutonium (Pu) isotopes, and improve upon the uncertainty of today's confirmatory methods is needed. Lead slowing-down spectroscopy (LSDS) has been studied for the spent fuel application previously, but the nonlinear effects of assembly self shielding (of the interrogating neutron population) have led to discouraging assay accuracy for realistic pressurized water reactor fuels. In this paper, we describe the development of time-spectral analysis algorithms for LSDS intended to overcome these self-shielding effects. The algorithm incorporates the tabulated energy-dependent cross sections from key fissile and absorbing isotopes, but leaves their mass as free variables. Multi-parameter regression analysis is then used to directly calculate not only the mass of fissile isotopes in the fuel assembly (e.g., Pu-239, U-235, and Pu-241), but also the mass of key absorbing isotopes such as Pu-240 and U-238. Modeling-based assay results using this self-shielding relationship indicate that LSDS has the potential to directly measure fissile isotopes with less than 5% average relative error for pressurized water reactor assemblies with burnup as high as 60 GWd/MTU. Shortcomings in the initial self-shielding model and potential improvements to the formulation are described.Index Terms-Neutron spectroscopy, nondestructive assay, nuclear fuel cycle safeguards, nuclear fuels.

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“…This is the so-called differential die-away analysis (DDAA) method. A stochastic generalisation of this method, to the use of a stationary (intrinsic) source and the measurement of the time correlations, the so-called DDSI (differential die-away self interrogation) method, was recently suggested by Menlove et al [13]. The theory of the DDSI method, by way of the extension of the Rossi-alpha method to two energy groups, without delayed neutrons, was recently given by the present authors based on both the backward [14] and the forward master equation approach [15].…”

Section: Introductionmentioning

confidence: 99%

Two-Group Theory of the Feynman-Alpha Method for Reactivity Measurement in ADS

Пал

Pázsit

2012

Science and Technology of Nuclear Installations

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The theory of the Feynman-alpha method, which is used to determine the subcritical reactivity of systems driven by an external source such as an ADS, is extended to two energy groups with the inclusion of delayed neutrons. This paper presents a full derivation of the variance to mean formula with the inclusion of two energy groups and delayed neutrons. The results are illustrated quantitatively and discussed in physical terms.

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

Cited by 28 publications

References 1 publication

A general analytical solution for the variance-to-mean Feynman-alpha formulas for a two-group two-point, a two-group one-point and a one-group two-point cases

A general analytical solution for the variance-to-mean Feynman-alpha formulas for a two-group two-point, a two-group one-point and a one-group two-point cases

Time-Spectral Analysis Methods for Spent Fuel Assay Using Lead Slowing-Down Spectroscopy

Two-Group Theory of the Feynman-Alpha Method for Reactivity Measurement in ADS

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