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Tuesday, August 11, 2020 | History

3 edition of Statistical precision of delayed-neutron nondestructive assay techniques found in the catalog.

Statistical precision of delayed-neutron nondestructive assay techniques

C. K. Bayne

Statistical precision of delayed-neutron nondestructive assay techniques

by C. K. Bayne

  • 242 Want to read
  • 34 Currently reading

Published by Dept. of Energy, Oak Ridge National Laboratory, for sale by the National TechnicaL Information Service] in OaK Ridge, Tenn, [Springfield, Va .
Written in English

    Subjects:
  • Delayed neutrons,
  • Nuclear fuels -- Testing,
  • Isotopes -- Measurement

  • Edition Notes

    StatementC. K.Bayne and S. R. McNeany
    SeriesORNL/TM ; 6569
    ContributionsMcNeany, S. R., joint author, Oak Ridge National Laboratory. Metals and Ceramics Division
    The Physical Object
    Paginationv, 29 p. :
    Number of Pages29
    ID Numbers
    Open LibraryOL14881695M

    QA/QC includes steps such as calibrating instruments or measurements against known standards, reporting all instrument detection limits, implementing standardized procedures to minimize human error, thoroughly documenting research methods, replicating measurements to determine precision, and a host of other techniques, often specific to the. Calorimetry is a nondestructive assay technique for determining the thermal power output of heat-producing nuclear materials. Calorimeter systems are used to determine the power output (Watts) of various radionuclides over a broad range of power levels and sample types (Pu, highly enriched uranium, and Tritium).

    This test method describes the nondestructive assay of plutonium in forms such as metal, oxide, scrap, residue, or waste using passive neutron multiplicity counting. This test method provides results that are usually more accurate than conventional neutron coincidence counting. The method can be applied to a large variety of plutonium items in various containers including . Nondestructive Assay (NDA) Personnel 1 This test method is under the jurisdiction ofASTM Committee C26 on Nuclear C Guide for Nondestructive Assay Measurements Fuel Cycle and is the direct responsibility of Subcommittee C on Non Destructive Assay. Currenteditionapproved June 1, Published July Originallyapproved in

    guide to nondestructive assay (NDA) techniques to aid the user in matching instruments with measurement problems. The. figures and tables of this chapter refer to many of the measurement techniques described earlier in the book; several important active techniques are also included. Addhional infor-. ASTM's quality control standards provide the mathematical and statistical procedures instrumental in the evaluation of experiments and test methods. These procedures encompass the information-gathering stage of an experiment where variation is present, and includes the probability sampling process, the determination of the precision and bias of.


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Statistical precision of delayed-neutron nondestructive assay techniques by C. K. Bayne Download PDF EPUB FB2

Get this from a library. Statistical precision of delayed-neutron nondestructive assay techniques. [C K Bayne; S R McNeany; Oak Ridge National. Statistical precision of delayed-neutron nondestructive assay techniques. Technical Report Bayne, C. K.; McNeany, S. A theoretical analysis of the statistical precision of delayed-neutron nondestructive assay instruments is presented.

Such instruments measure the fissile content of nuclear fuel samples by neutron irradiation and delayed. We concluded that it is possible to assay 1% actinide content in the spent fuel with % (R=2) and % (R=) statistical precision during s measurement time for the NRF peak at E γ = – 5 MeV with the total integrated cross-section of 30 eV b by using a photon beam with an intensity of 10 6 photons/s/ by: 1.

In the fields of science and engineering, the accuracy of a measurement system is the degree of closeness of measurements of a quantity to that quantity's true value.

The precision of a measurement system, related to reproducibility and repeatability, is the degree to which repeated measurements under unchanged conditions show the same results.

Although the two words precision. @article{osti_, title = {Passive nondestructive assay of nuclear materials}, author = {Reilly, D and Ensslin, N and Smith, H Jr and Kreiner, S}, abstractNote = {The term nondestructive assay (NDA) is applied to a series of measurement techniques for nuclear fuel materials.

The techniques measure radiation induced or emitted spontaneously from the. A variety of nondestructive assay (NDA) techniques are available to quantify these signatures. The effort presented in this paper is investigation the capabilities of 12 NDA techniques.

A modulated Cf source assay system “Shuffler” based on fast-or-thermal-neutron interrogation combined with delayed-neutron counting has been developed for the assay of fissile material. The Cf neutron source is repetitively transferred from the interrogation position to a shielded position while the delayed neutrons are counted in a high.

can benefit from these techniques for non-destructive assay of. statistical uncertainty lower then 1%, the total uncertainty high and currently limits the precision of the delayed neutron. The nondestructive assay reference; Passive Nondestructive Assay of Nuclear Material; Reilly, Ensslin, Smith, and Kreiner, was published in although the major technical writing was completed by This book has become widely known by the acronym PANDA.

Although much of the material contained. An uncertainty analysis of non-destructive assay of spent fuel using a delayed neutron method was conducted to explicitly define the accuracy with which plutonium content in an uncharacterized. nondestructive nuclear methods). The assay of feed, product, scrap, and waste is considered.

Ranges of accuracy and precision are given. CHAPTER 1 INTRODUCTION SCOPE This report is designed to be a source book for reliability data relevant to nondestructive assay measurements.

Comparing data from any plant with data given here permits evaluation of. The outside walls of the cell are made of polyethylene to shield the device from external neutrons. The interrogating neutron flux is produced by a new generation 14 MeV pulsed neutron generator, the emission of which is about 2×10 9 n s −te is a neutron moderator which is used to optimise the die away time of thermal neutron interrogating flux inside the cell.

Request PDF | MONTE CARLO ERROR ESTIMATION APPLIED TO NONDESTRUCTIVE ASSAY METHODS | Monte Carlo randomization of nuclear counting data into N replicate sets is the basis of a simple and effective. A statistical analysis of the measurement performance of five mobile nondestructive assay systems currently in use for radioassay of nuclear waste was performed.

Actual versus reported isotopic mass composition, reported versus actual measurement uncertainty, detection capability, and low level versus transuranic waste determination were.

Assay Validation: Comprehensive experiments that evaluate and document the quantitative performance of an assay, including sensitivity, specificity, accuracy, precision, detection limit, range and limits of quantitation. Full Assay Validation will include inter-assay and inter-laboratory assessment of assay repeatability and robustness.

However, conventional methods for the evaluation of the glass and filler contents of reinforced plastics are destructive, labor intensive, and time consuming. We have developed a new instrument, to address this problem, which provides for the rapid, accurate, and nondestructive measurement of glass or filler content in reinforced plastics.

The measurement of DN emissions from fissioned SNM has been identified as a valuable nuclear forensics tool as it is a non-destructive, rapid, and an accurate form of assay [3,[8][9][10].

search in techniques for nondestructive assay of fis- sionable materials. Monoenergetic neutrons make An Example: Small Sample Assay bv Delayed-Neutron Counting The Van de Graaff has provided us with our most effective method for assay of U in small sam- precision, are of coursedetermined by the product of.

The paper describes an automated non-destructive assay (NDA) system for the measurement and characterization of radioactive waste. The Waste Characterisation System (WCS) can be adapted to measure a variety of drum sizes: 60, (55 gallon) and liter, the latter with a maximum weight of kg ( tonnes).

High-­energy, beta-delayed gamma-­ray spectroscopy is a potential, non-­destructive assay techniques for the independent verification of declared quantities of special nuclear materials at key stages of the fuel cycle and for directly assaying nuclear material inventories for spent fuel handling, interim storage, reprocessing facilities.

It contains several useful statistical formulas and procedures for estimating assay errors. The discussion considers random errors (assay precision) only. There is no consideration of the often serious problem of systematic errors (assay bias).

For a more thorough discussion of assay precision and bias, please refer to textbooks on statistics.Prior to disposal, nuclear waste must be accurately characterized to identify and quantify the radioactive content.

The DOE Complex faces the daunting task of measuring nuclear material with both a wide range of masses and matrices. Similarly daunting can be the selection of a non-destructive assay.Jaech J () statistical methods in nuclear materials control, U.S. Atomic Energy Commission Google Scholar 4. Burr T, Coulter C, Hakkila E, Ai H, Kadokura I, and Fujimaki K () Statistical methods for detecting loss of materials using near-real time accounting data.

36th Annual Meeting of the Institute of Nuclear Materials Management.