Analysis of Spent Fuel Assay with a Lead Slowing Down Spectrometer

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Download or read book Analysis of Spent Fuel Assay with a Lead Slowing Down Spectrometer written by and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Assay of fissile materials in spent fuel that are produced or depleted during the operation of a reactor, is of paramount importance to nuclear materials accounting, verification of the reactor operation history, as well as for criticality considerations for storage. In order to prevent future proliferation following the spread of nuclear energy, we must develop accurate methods to assay large quantities of nuclear fuels. We analyze the potential of using a Lead Slowing Down Spectrometer for assaying spent fuel. We conclude that it is possible to design a system that will provide around 1% statistical precision in the determination of the 239Pu, 241Pu and 235U concentrations in a PWR spent-fuel assembly, for intermediate-to-high burnup levels, using commercial neutron sources, and a system of 238U threshold fission detectors. Pending further analysis of systematic errors, it is possible that missing pins can be detected, as can asymmetry in the fuel bundle.

Lead Slowing-Down Spectrometry for Spent Fuel Assay

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Book Synopsis Lead Slowing-Down Spectrometry for Spent Fuel Assay by :

Download or read book Lead Slowing-Down Spectrometry for Spent Fuel Assay written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Executive Summary The Office of Nuclear Energy, Fuel Cycle R & D, Material Protection and Control Technology (MPACT) Campaign is supporting a multi-institutional collaboration to study the feasibility of using Lead Slowing Down Spectroscopy (LSDS) to conduct direct, independent and accurate assay of fissile isotopes in used fuel assemblies. The collaboration consists of Pacific Northwest National Laboratory (PNNL), Los Alamos National Laboratory (LANL), Rensselaer Polytechnic Institute (RPI), Idaho State University (ISU). There are three main challenges to implementing LSDS to assay used fuel assemblies. These challenges are the development of an algorithm for interpreting the data with an acceptable accuracy for the fissile masses, the development of suitable detectors for the technique, and the experimental benchmarking of the approach. This report is a summary of the progress in these areas made by the collaboration during FY2012. Significant progress was made on the project in FY2012. Extensive characterization of a?semi-empirical? algorithm was conducted. For example, we studied the impact on the accuracy of this algorithm by the minimization of the calibration set, uncertainties in the calibration masses, and by the choice of time window. Issues such a lead size, number of required neutrons, placement of the neutron source and the impact of cadmium around the detectors were also studied. In addition, new algorithms were developed that do not require the use of plutonium fission chambers. These algorithms were applied to measurement data taken by RPI and shown to determine the 235U mass within 4%. For detectors, a new concept for a fast neutron detector involving 4He recoil from neutron scattering was investigated. The detector has the potential to provide a couple of orders of magnitude more sensitivity than 238U fission chambers. Progress was also made on the more conventional approach of using 232Th fission chambers as fast neutron detectors. For benchmarking measurements, we continue to improve our understanding of the experimental setup by studying issues such as the effect of room return and impurities in the lead. RPI performed a series of experiments with a fresh fuel pin and various 235U and 239Pu sources. A comparison between simulations and measurements shows significant deviations after 200 æs for both 235U and 239Pu samples, as well as significant deviations at earlier times for the 239Pu sample. The FY2013 effort will shift focus to planning for a Technical Readiness Level 5 demonstration. The primary deliverable for the year will be a plan on how to do this demonstration. The plan will include measurement design, sample acquisition, sample handling, cost estimate, schedule and assumptions. Research will continue on the 4He detector, algorithms development, thorium fission chambers and benchmarking measurements involving sub assemblies of fresh fuel.

Lead Slowing-down Spectrometry Time Spectral Analysis for Spent Fuel Assay

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Download or read book Lead Slowing-down Spectrometry Time Spectral Analysis for Spent Fuel Assay written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Lead Slowing-down Spectrometry Time Spectral Analysis for Spent Fuel Assay

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Book Synopsis Lead Slowing-down Spectrometry Time Spectral Analysis for Spent Fuel Assay by :

Download or read book Lead Slowing-down Spectrometry Time Spectral Analysis for Spent Fuel Assay written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Developing a method for the accurate, direct, and independent assay of the fissile isotopes in bulk materials (such as used fuel) from next-generation domestic nuclear fuel cycles is a goal of the Office of Nuclear Energy, Fuel Cycle R & D, Material Protection and Control Technology (MPACT) Campaign. To meet this goal, MPACT supports a multi-institutional collaboration, of which PNNL is a part, to study the feasibility of Lead Slowing Down Spectroscopy (LSDS). This technique is an active nondestructive assay method that has the potential to provide independent, direct measurement of Pu and U isotopic masses in used fuel with an uncertainty considerably lower than the approximately 10% typical of today's confirmatory assay methods. This document is a progress report for FY2011 PNNL analysis and algorithm development. Progress made by PNNL in FY2011 continues to indicate the promise of LSDS analysis and algorithms applied to used fuel. PNNL developed an empirical model based on calibration of the LSDS to responses generated from well-characterized used fuel. The empirical model, which accounts for self-shielding effects using empirical basis vectors calculated from the singular value decomposition (SVD) of a matrix containing the true self-shielding functions of the used fuel assembly models. The potential for the direct and independent assay of the sum of the masses of 239Pu and 241Pu to within approximately 3% over a wide used fuel parameter space was demonstrated. Also, in FY2011, PNNL continued to develop an analytical model. Such efforts included the addition of six more non-fissile absorbers in the analytical shielding function and the non-uniformity of the neutron flux across the LSDS assay chamber. A hybrid analytical-empirical approach was developed to determine the mass of total Pu (sum of the masses of 239Pu, 240Pu, and 241Pu), which is an important quantity in safeguards. Results using this hybrid method were of approximately the same accuracy as the pure empirical approach. In addition, total Pu with much better accuracy with the hybrid approach than the pure analytical approach. In FY2012, PNNL will continue efforts to optimize its empirical model and minimize its reliance on calibration data. In addition, PNNL will continue to develop an analytical model, considering effects such as neutron-scattering in the fuel and cladding, as well as neutrons streaming through gaps between fuel pins in the fuel assembly.

Lead Slowing-Down Spectrometry for Spent Fuel Assay

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Book Synopsis Lead Slowing-Down Spectrometry for Spent Fuel Assay by :

Download or read book Lead Slowing-Down Spectrometry for Spent Fuel Assay written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Executive Summary Developing a method for the accurate, direct, and independent assay of the fissile isotopes in bulk materials (such as used fuel) from next-generation domestic nuclear fuel cycles is a goal of the Office of Nuclear Energy, Fuel Cycle R & D, Material Protection and Control Technology (MPACT) Campaign. To meet this goal, MPACT supports a multi-institutional collaboration to study the feasibility of Lead Slowing Down Spectroscopy (LSDS). This technique is an active nondestructive assay method that has the potential to provide independent, direct measurement of Pu and U isotopic masses in used fuel with an uncertainty considerably lower than the approximately 10% typical of today's confirmatory assay methods. This document is a progress report for FY2011 collaboration activities. Progress made by the collaboration in FY2011 continues to indicate the promise of LSDS techniques applied to used fuel. PNNL developed an empirical model based on calibration of the LSDS to responses generated from well-characterized used fuel. The empirical model demonstrated the potential for the direct and independent assay of the sum of the masses of 239Pu and 241Pu to within approximately 3% over a wide used fuel parameter space. Similar results were obtained using a perturbation approach developed by LANL. Benchmark measurements have been successfully conducted at LANL and at RPI using their respective LSDS instruments. The ISU and UNLV collaborative effort is focused on the fabrication and testing of prototype fission chambers lined with ultra-depleted 238U and 232Th, and uranium deposition on a stainless steel disc using spiked U3O8 from room temperature ionic liquid was successful, with improving thickness obtained. In FY2012, the collaboration plans a broad array of activities. PNNL will focus on optimizing its empirical model and minimizing its reliance on calibration data, as well continuing efforts on developing an analytical model. Additional measurements are planned at LANL and RPI. LANL measurements will include a Pu sample, which is expected to provide more counts at longer slowing-down times to help identify discrepancies between experimental data and MCNPX simulations. RPI measurements will include the assay of an entire fresh fuel assembly for the study of self-shielding effects as well as the ability to detect diversion by detecting a missing fuel pin in the fuel assembly. The development of threshold neutron sensors will continue, and UNLV will calibrate existing ultra-depleted uranium deposits at ISU.

Lead Slowing-down Spectroscopy for Spent Fuel Assay

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Book Synopsis Lead Slowing-down Spectroscopy for Spent Fuel Assay by :

Download or read book Lead Slowing-down Spectroscopy for Spent Fuel Assay written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Spent Fuel Assay with a Lead Slowing Down Spectrometer LANSCE Experiments

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Book Synopsis Spent Fuel Assay with a Lead Slowing Down Spectrometer LANSCE Experiments by :

Download or read book Spent Fuel Assay with a Lead Slowing Down Spectrometer LANSCE Experiments written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Measurement and Analysis Plan for Investigation of Spent-Fuel Assay Using Lead Slowing-Down Spectroscopy

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Book Synopsis Measurement and Analysis Plan for Investigation of Spent-Fuel Assay Using Lead Slowing-Down Spectroscopy by :

Download or read book Measurement and Analysis Plan for Investigation of Spent-Fuel Assay Using Lead Slowing-Down Spectroscopy written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Under funding from the Department of Energy Office of Nuclear Energy's Materials, Protection, Accounting, and Control for Transmutation (MPACT) program (formerly the Advanced Fuel Cycle Initiative Safeguards Campaign), Pacific Northwest National Laboratory (PNNL) and Los Alamos National Laboratory (LANL) are collaborating to study the viability of lead slowing-down spectroscopy (LSDS) for spent-fuel assay. Based on the results of previous simulation studies conducted by PNNL and LANL to estimate potential LSDS performance, a more comprehensive study of LSDS viability has been defined. That study includes benchmarking measurements, development and testing of key enabling instrumentation, and continued study of time-spectra analysis methods. This report satisfies the requirements for a PNNL/LANL deliverable that describes the objectives, plans and contributing organizations for a comprehensive three-year study of LSDS for spent-fuel assay. This deliverable was generated largely during the LSDS workshop held on August 25-26, 2009 at Rensselaer Polytechnic Institute (RPI). The workshop itself was a prominent milestone in the FY09 MPACT project and is also described within this report.

Lead Slowing Down Spectrometer Research Plans

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Book Synopsis Lead Slowing Down Spectrometer Research Plans by :

Download or read book Lead Slowing Down Spectrometer Research Plans written by and published by . This book was released on 2013 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Lead Slowing Down Spectrometer Assay Measurements of a Simulated Fuel Bundle

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Book Synopsis Lead Slowing Down Spectrometer Assay Measurements of a Simulated Fuel Bundle by : Floyd W. Bornt (Jr)

Download or read book Lead Slowing Down Spectrometer Assay Measurements of a Simulated Fuel Bundle written by Floyd W. Bornt (Jr) and published by . This book was released on 1981 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Lead Slowing Down Spectrometer Status Report

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Book Synopsis Lead Slowing Down Spectrometer Status Report by :

Download or read book Lead Slowing Down Spectrometer Status Report written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report documents the progress that has been completed in the first half of FY2012 in the MPACT-funded Lead Slowing Down Spectrometer project. Significant progress has been made on the algorithm development. We have an improve understanding of the experimental responses in LSDS for fuel-related material. The calibration of the ultra-depleted uranium foils was completed, but the results are inconsistent from measurement to measurement. Future work includes developing a conceptual model of an LSDS system to assay plutonium in used fuel, improving agreement between simulations and measurement, design of a thorium fission chamber, and evaluation of additional detector techniques.

The Application of the Slowing Down Spectrometer to Nuclear Materials Assay

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Total Pages : 36 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis The Application of the Slowing Down Spectrometer to Nuclear Materials Assay by : J. R. Beyster

Download or read book The Application of the Slowing Down Spectrometer to Nuclear Materials Assay written by J. R. Beyster and published by . This book was released on 1970 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Lead Slowing Down Spectrometer FY2013 Annual Report

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Book Synopsis Lead Slowing Down Spectrometer FY2013 Annual Report by :

Download or read book Lead Slowing Down Spectrometer FY2013 Annual Report written by and published by . This book was released on 2013 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Executive Summary The Lead Slowing Down Spectrometry (LSDS) project, funded by the Materials Protection And Control Technology campaign, has been evaluating the feasibility of using LSDS techniques to assay fissile isotopes in used nuclear fuel assemblies. The approach has the potential to provide considerable improvement in the assay of fissile isotopic masses in fuel assemblies compared to other non-destructive techniques in a direct and independent manner. This report is a high level summary of the progress completed in FY2013. This progress included: - Fabrication of a 4He scintillator detector to detect fast neutrons in the LSDS operating environment. Testing of the detector will be conducted in FY2014. - Design of a large area 232Th fission chamber. - Analysis using the Los Alamos National Laboratory perturbation model estimated the required number of neutrons for an LSDS measurement to be 10 to the 16th source neutrons. - Application of the algorithms developed at Pacific Northwest National Laboratory to LSDS measurement data of various fissile samples conducted in 2012. The results concluded that the 235U could be measured to 2.7% and the 239Pu could be measured to 6.3%. Significant effort is yet needed to demonstrate the applicability of these algorithms for used-fuel assemblies, but the results reported here are encouraging in demonstrating that we are making progress toward that goal. - Development and cost-analysis of a research plan for the next critical demonstration measurements. The plan suggests measurements on fresh fuel sub assemblies as a means to experimentally test self-attenuation and the use of fresh mixed-oxide fuel as a means to test simultaneous measurement of 235U and 239Pu.

Nondestructive Fissile Material Assay with the Lead Slowing-down-time Spectrometer in the 1 to 1000 EV Neutron Energy Range

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Total Pages : 636 pages
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Book Synopsis Nondestructive Fissile Material Assay with the Lead Slowing-down-time Spectrometer in the 1 to 1000 EV Neutron Energy Range by : James Edward Rushton

Download or read book Nondestructive Fissile Material Assay with the Lead Slowing-down-time Spectrometer in the 1 to 1000 EV Neutron Energy Range written by James Edward Rushton and published by . This book was released on 1975 with total page 636 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Determination of Plutonium Content in Spent Fuel with Nondestructive Assay

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Total Pages : 11 pages
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Book Synopsis Determination of Plutonium Content in Spent Fuel with Nondestructive Assay by :

Download or read book Determination of Plutonium Content in Spent Fuel with Nondestructive Assay written by and published by . This book was released on 2009 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: There are a variety of reasons for quantifying plutonium (Pu) in spent fuel such as independently verifying the Pu content declared by a regulated facility, making shipper/receiver mass declarations, and quantifying the input mass at a reprocessing facility. As part of the Next Generation Safeguards Initiative, NA-241 has recently funded a multilab/university collaboration to determine the elemental Pu mass in spent fuel assemblies. This research effort is anticipated to be a five year effort: the first part of which is a two years Monte Carlo modeling effort to integrate and down-select among 13 nondestructive assay (NDA) technologies, followed by one year for fabricating instruments and then two years for measuring spent fuel. This paper gives a brief overview of the approach being taken for the Monte Carlo research effort. In addition, preliminary results for the first NDA instrument studied in detail, delayed neutron detection, will be presented. In order to cost effectively and robustly model the performance of several NDA techniques, an"assembly library" was created that contains a diverse range of pressurized water reactor spent fuel assemblies (burnup, enrichment, cooling time) similar to that which exists in spent pools today and in the future, diversion scenarios that capture a range of possible rod removal options, spatial and isotopic detail needed to accurately quantify the capability of all the NDA techniques so as to enable integration. Integration is being designed into this study from the beginning since it is expected that the best performance will be obtained by combining a few NDA techniques. The performance of each instrument will be quantified for the full assembly library in three different media: air, water and borated water. In this paper the preliminary capability of delayed neutron detection will be quantified for the spent fuel library for all three media. The 13 NDA techniques being researched are the following: Delayed Gamma, Delayed Neutrons, Differential Die-Away, Differential Die-Away Self-Interrogation, Lead Slowing Down Spectrometer, Neutron Multiplicity, Nuclear Resonance Fluorescence, Passive Prompt Gamma, Passive Neutron Albedo Reactivity, Self-integration Neutron Resonance Densitometry, Total Neutron (Gross Neutron), X-Ray Fluorescence, 252Cf Interrogation with Prompt Neutron Detection.

The Development of a Lead Slowing-down-time Spectrometer for Fissile Material Assay and Fast Reactor Physics Research

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Total Pages : 560 pages
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Book Synopsis The Development of a Lead Slowing-down-time Spectrometer for Fissile Material Assay and Fast Reactor Physics Research by : Thomas Leland Atwell

Download or read book The Development of a Lead Slowing-down-time Spectrometer for Fissile Material Assay and Fast Reactor Physics Research written by Thomas Leland Atwell and published by . This book was released on 1973 with total page 560 pages. Available in PDF, EPUB and Kindle. Book excerpt:

NUREG/CR.

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Total Pages : 420 pages
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Book Synopsis NUREG/CR. by : U.S. Nuclear Regulatory Commission

Download or read book NUREG/CR. written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1981 with total page 420 pages. Available in PDF, EPUB and Kindle. Book excerpt: