Production of actinide isotopes in simulated PWR fuel and their influence on inherent neutron emission

Bosler, G.E.; Phillips, J. R.; Wilson, W.B.; LaBauve, R.J.; England, T.R.

doi:10.2172/5113091

Cited by 9 publications

(3 citation statements)

References 7 publications

(2 reference statements)

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“…Atom densities for uranium and plutonium isotopes have been obtained from CINDER calculations for the H. B. Robinson PWR fuel. 51 ' 52 The calculated atom densities compare closely with data obtained from destructive analysis of this fuel that had been irradiated up to 30 000 MWd/tU. A plot of the calculated atom densities vs burnup is shown in Fig.…”

Section: Spent-fuel Composition Prompt and Delayed Neutron Emissionssupporting

confidence: 58%

Nuclear safeguards research and development. Program status report, October 1980-January 1981

Henry

1981

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This report presents tho status of the Nuclear Safeguards Research and Development Program pursued by the Energy, Chemistry-Materials Science, and Operational Security/Safeguards IHvisions of the Los Alamos National Laboratory. Topics include nondestructive assay technology development and applications, international safeguards, <>srimeter safeguards and surveillance, concepts and subsystems development, and integrated safeguards systems. Also discussed are training courses, technology transfer, analytical chemistry methods for fissionable materials safeguards, the Department of Energy Computer Security Technical Center, and operational security. PART I SAFEGUARDS TECHNOLOGY I. TEST AND EVALUATION PROGRAMS AT DEPARTMENT OF ENERGY FACILITIES A. Test and Evaluation of the In-Line Plutonium Solu-precisions achieved over this wider concentration range, tion Densitometer at the Savannah River Plant (H. A. and Fig. 2 compares the densitometer assay results with Smith, T. Marks, S. S. Johnson, R. W. Slice, J. K. the corresponding chemical analyses. Figure 1 demon-Sprinkle, L. R. Cowder, C. O. Shonrock, and D. L. strates that the densitometer can achieve better than Garcia) 0.5% statistical assay precision on plutonium concentrations ranging from 30 to > 100 g Pu#. Figure 2 shows Off-line measurements with the K-edge plutonium excellent agreement between the densitometer and solution densitometer 1 have continued. Concentrations chemical assays over the design range (and the range of measured standards have been extended from the over which the calibration was established, as described design range of 25 to 40 g Pu/V to a range of 5 to 200 g in Ref. 2) and very good agreement beyond that range. P#. Figure 1 summarizes the instrument densitometry The discrepancy at 200 g/(points out the limitation of % w a D°" 1.0 0.5 INSTRUMENT DENSITOMETRY ASSAY PRECISION ond Z9mCi S7 Co 20-mln dsnsitomstry assay-40-roln dtn*ltom«try assay

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Section: Spent-fuel Composition Prompt and Delayed Neutron Emissionssupporting

confidence: 58%

Nuclear safeguards research and development. Program status report, October 1980-January 1981

Henry

1981

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“…This larger deviation can be understood by looking closer at its production pathway which is shown in Eqs. ( 2) and (3) wherein it can be seen that 241 Am is a nuclide that continues to form after the reactor has been shutdown or alternatively, after the fuel has been discharged (Bosler et al, 1982). From Fig.…”

Section: Realistic Power History Versus Simplified Power Historymentioning

confidence: 97%

“…Several studies (Bosler et al, 1982;Tomatis et al, 2017;Sweeney and Charlton, 2008) in the past have looked into estimating the impact and quantification of individual isotopic sensitivities to irradiation parameters of the SNF. However, due to the lack of availability of detailed power history data from NPPs, it is often difficult to assess whether idealization or finding a representative power history is at all feasible for modeling fuel irradiation in the core.…”

Section: Introductionmentioning

confidence: 99%

Statistical Analysis of Fuel Cycle Data from Swedish Pressurized Water Reactors and the Impact of Simplifying Assumptions on Simulated Nuclide Inventories

Mishra

Elter²,

Branger³

et al. 2022

SSRN Journal

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Spent Fuel Measurements

Kaplan-Trahan,

Belian,

Croce

et al. 2024

Nondestructive Assay of Nuclear Materials for Safeguards and Security

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This chapter describes the methods used to measure spent nuclear fuel. The first section describes the properties of typical reactor fuel: geometry, burnup, initial enrichment, and cooling time. Neutron multiplication in the assembly is discussed. The measurement methods are divided into gamma-based methods, neutron-based methods, and other methods. A particularly important gamma-based method is passive gamma emission tomography. The neutron-based methods range from the relatively simple passive neutron fork, passive neutron albedo reactivity and differential dieaway to the complex active methods. The other methods are Cerenkov viewing devices, curium/plutonium ratio and calorimetry.

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Production of actinide isotopes in simulated PWR fuel and their influence on inherent neutron emission

Cited by 9 publications

References 7 publications

Nuclear safeguards research and development. Program status report, October 1980-January 1981

Nuclear safeguards research and development. Program status report, October 1980-January 1981

Statistical Analysis of Fuel Cycle Data from Swedish Pressurized Water Reactors and the Impact of Simplifying Assumptions on Simulated Nuclide Inventories

Spent Fuel Measurements

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