Preliminary concepts: coordinated safeguards for materials management in a thorium--uranium fuel reprocessing plant

Hakkila, E.A.; Barnes, J.W.; Dayem, H.A.; Dietz, R.J.; Shipley, J.P.

doi:10.2172/6536546

Cited by 9 publications

(12 citation statements)

References 4 publications

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“…variance 1) MUF residuals. Page's Test is intimately connected with the VMask procedures from quality control, which was noted in Hakkila et al (1977), Stewart and Wincek (1978) and Wincek et al (1979). In the last reference it was suggested that these procedures should be applied to what was there called the MUF innovation sequence, a sequence which in fact coincides with the MUF residuals.…”

Section: Survey Of Work In Nuclear Materials Accountingmentioning

confidence: 93%

“…General sequential statistical procedures are outlined in Cobb et al (1976), Hakkila et al (1977), Shipley (1978aShipley ( , 1978bShipley ( , 1981Shipley ( , 1983, Cobb and Shipley (1979) and Cobb (1981). In particular, the cusum and sequential probability ratio tests (SPRT) are described in these papers and the implementation of the latter worked out for state space models.…”

Section: Survey Of Work In Nuclear Materials Accountingmentioning

confidence: 99%

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The Role of Statistics in Nuclear Materials Accounting: Issues and Problems

Speed¹,

Culpin²

1986

Journal of the Royal Statistical Society. Series A (General)

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Section: Survey Of Work In Nuclear Materials Accountingmentioning

confidence: 93%

Section: Survey Of Work In Nuclear Materials Accountingmentioning

confidence: 99%

The Role of Statistics in Nuclear Materials Accounting: Issues and Problems

Speed¹,

Culpin²

1986

Journal of the Royal Statistical Society. Series A (General)

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“…Any other convex cost function can be used for each measurement uncertainty component. The relative cost (C.) of improving the i measurement error component is given by (2) where A. = relative improvement difficulty factor for a., a .…”

Section: B Cost Functionsmentioning

confidence: 99%

“…The materials balance variance for a given accounting area can be computed by summing its appropriate inventory and transfer variances. Equation (NCAT) 2 column 5. These standard deviations are generally thought to be achievable with current technology (see Sec.…”

Section: A Transfer As One Measured Value (Type 1)mentioning

confidence: 99%

Materials accounting in a fast-breeder-reactor fuels-reprocessing facility: optimal allocation of measurement uncertainties

Dayem¹,

Ostenak²,

Gutmacher³

et al. 1982

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EXECUTIVE SUMMARYThis report describes the first in a series of studies in support of the US Department of Energy's (DOE) Consolidated Fuel Reprocessing Program. These studies develop and evaluate designs of advanced materials measurement and accounting systems (MMASs) for various nuclear spent-fuel reprocessing alternatives. This report examines safeguards design concepts for the feed preparation and chemical separations processes of the Hot Experimental Facility (HEF), a conceptual fast breeder reactor spent-fuel reprocessing facility. We propose an MMAS and use optimization techniques to calculate instrument measurement uncertainties that meet four different accounting performance goals while minimizing the total development cost of instrument systems. We identify measurement uncertainty components that dominate the materials balance variance and instruments that require development to meet given performance goals.Conceptual design efforts for MMASs are a major portion of an integrated safeguards systems study program that is implemented by the Safeguards Systems Group (Q-4) of the Los Alamos National Laboratory, at the direction of the US DOE/Office of Safeguards and Security. These designs invoke technology that has been demonstrated or can be projected within the construction schedules of future nuclear fuel-cycie facilities. The studies define systems concepts, develop methods for evaluating safeguards systems and the data they produce, and should stimulate further development of facilities, processes, systems, and instrumentation needed for improving nuclear materials accounting, thus providing more effective safeguards.Previous Los Alamos National Laboratory studies in the safeguards conceptual design series address the materials management requirements for mixed-oxide fuel refabrication facilities (LA-6536), domestic and foreign spent-fuel reprocessing plants (LA-6881 and LA-8042), plutonium nitrate conversion (LA-7011) and coconversion facilities (LA-7521 and LA-7746-MS), spent-fuel storage ponds (LA-7730-MS), thorium-uranium fuel-cycle facilities (LA-7372 and LA-7411-MS), large fast-critical reactors (LA-7315), and nuclear waste repositories (LA-8049-MS). In general, these studies calculate the accounting systems performance by proposing a measurement system based on current technology or its reasonable extrapolations. The measurement uncertainties for each proposed instrument are then combined and propagated to obtain an overall materials loss-detection sensitivity.This study reverses the approach. We select specific accounting performance goals for the HEF and use optimization techniques to calculate measurement uncertainties required to meet these goals while minimizing the total development cost of the instrument system.The design for Oak Ridge National Laboratory's HEF incorporates a modified Purex process that allows coprocessing uranium and plutonium. The flow sheet is based on reprocessing 0.5 tonne/day of breeder reactor fuel having (1) a maximum burnup of 150 000 megawatt-days per tonne, (2)...

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“…Variance and covariance terms are estimated by replacing the true quantities y in Eqs. (5) and (6) by the appropriate measured quantities.…”

Section: ^2mentioning

confidence: 99%

Coordinated safeguards for materials management in a uranium--plutonium nitrate-to-oxide coconversion facility: Coprecal

Dayem¹,

Cobb²,

Dietz³

et al. 1979

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This report describes the conceptual design of an advanced materials-management system for safeguarding special nuclear materials in a uranium-plutonium nitrate-to-oxide coconversion facility based on the Coprecal process. Design concepts are presented for near real-time (dynamic) accountability by forming dynamic materials balances from information provided by chemical and nondestructive analyses and from process-control instrumentation. Modeling and simulation techniques are used to compare the sensitivities of proposed dynamic materials accounting strategies to both abrupt and protracted diversion. The safeguards implications of coconversion as well as some unique features of the reference process are discussed and design criteria are identified to improve the safeguardability of the Coprecal coconversion process. I.

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Preliminary concepts: coordinated safeguards for materials management in a thorium--uranium fuel reprocessing plant

Cited by 9 publications

References 4 publications

The Role of Statistics in Nuclear Materials Accounting: Issues and Problems

The Role of Statistics in Nuclear Materials Accounting: Issues and Problems

Materials accounting in a fast-breeder-reactor fuels-reprocessing facility: optimal allocation of measurement uncertainties

Coordinated safeguards for materials management in a uranium--plutonium nitrate-to-oxide coconversion facility: Coprecal

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