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Monday, August 3, 2020 | History

2 edition of Burnup Determination of Nuclear Fuels Using Neodymium-148. found in the catalog.

Burnup Determination of Nuclear Fuels Using Neodymium-148.

Atomic Energy of Canada Limited.

Burnup Determination of Nuclear Fuels Using Neodymium-148.

by Atomic Energy of Canada Limited.

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  • 19 Currently reading

Published by s.n in S.l .
Written in English


Edition Notes

1

SeriesAtomic Energy of Canada Limited. AECL -- 5964
ContributionsVandergraaf, T.T., Carefoot, L.M., Boase, D.G.
ID Numbers
Open LibraryOL21970543M

The mass-spectrometric and radiochemical methods for the determination of burn-up in nuclear fuel are compared for reliability in the range of to 15, Mwd/ton. Neither appears to be clearly superior to the other. Each appears to have an uncertainty of approximately 6 to 8%. The evolution of the high burn-up structure (HBS) in U(Mo) fuel irradiated up to a burn-up of ∼70% U or ∼5 × f/cm3 or ∼ GWd/tHM is described and compared to the observation made.

Fuel Burnup – Core Burnup. In nuclear engineering, fuel burnup (also known as fuel utilization) is a measure of how much energy is extracted from a nuclear fuel and a measure of fuel depletion. The most commonly defined as the fission energy release per unit mass of fuel in megawatt-days per metric ton of heavy metal of uranium (MWd/tHM), or similar units.   Introduction Neodymium is a very widely used fission product for burn-up determination in any type of fuel. It meets the required conditions for this usa ge. It is a stable isotope which appears only by fission in irradiated fuels.

In , Maeck proposed determination of nuclear fuel burnup based on the ratio of two stable fission product isotopes of the same element. Maeck proposed using, three ratios; [sup 84]Kr/[sup 83]Kr, [sup ]Xe/[sup ]Xe, and [sup ]Nd/[sup ]Nd. Articles in periodicals and books Abstract: The current paper reports the results of gamma spectroscopic burn-up determination and KüFA safety testing at JRC Karlsruhe on spherical high-temperature reactor fuel elements, which were fabricated by the Institute of Nuclear and New Energy Technology of the Tsinghua University, : Daniel Freis, Abdel El Abjani, Dragan Coric, Ramil Nasyrow, Joseph Somers, Chunhe Tang, Rongzheng Li.


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Burnup Determination of Nuclear Fuels Using Neodymium-148 by Atomic Energy of Canada Limited. Download PDF EPUB FB2

BURNUP DETERMINATION OF NUCLEAR FUELS USING NEODYMIUM by T.T. Vandergraaf, L.M. Carefoot and D.G. Boase ABSTRACT A method is described for determining the burnup of uranium and thorium-uranium fuels by measuring the Nd concentration in the fuel. The procedure involves separation of neodymium from dissolved.

The method covers the determination of stable fission product /sup /Nd in irradiated uranium (U) fuel (with initial plutonium (Pu) content from 0 to 50%) as a measure of fuel burnup. The method includes a discussion of significance and use, reagents and materials, instrument calibration, procedure, and calculations.

SUS, E. KLOSOVÁ, E. ŠTĚPÁNKOVÁ, V. FRAŇKOVÁ, Mass-spectrometric determination of burn up of nuclear fuel with the aid of Nd. Symposium on Research in the Field of Reprocessing of Irradiated Fuel, 28 March–1 April,Karlovy Vary, CSSR, Paper No. KV/ Google ScholarCited by: 1.

The primary nondestructive assay tool used by the International Atomic Energy Agency has been the fork detector irradiated fuel measurement system, which uses gross gamma and neutron correlations; however, there have been several research publications within the last decade on the use of high-resolution gamma spectroscopy for the determination.

Determination of plutonium and uranium content and burnup using six group delayed neutrons Article in Nuclear Engineering and Technology 51(4) July with 43 Reads How we measure 'reads'.

Burnup determination High burnup pressurized water reactor fuel Isotope dilution mass spectro-metric method Isotopic correlation abstract The correlation of the isotopic composition of uranium, plutonium, neodymium, and ce-sium with the burnup for high burnup pressurized water reactor fuels irradiated in nuclearFile Size: KB.

Integrated Nuclear Fuel Cycle Information System (iNFCIS) Net Enabled Waste Management Database (NEWMDB) Determination of Research Reactor Fuel Burnup, IAEA-TECDOC, IAEA, Vienna (). Download to: EdNote BibTeX *use BibTeX for Zotero. How to Access IAEA e-books.

Orders and requests for information may also be addressed to. INTERNATIONAL ATOMIC ENERGY AGENCY, Determination of Research Reactor Fuel Burnup, IAEA-TECDOC, IAEA, Vienna (). Download to. In this study, we calculated the burnup value and Pu conversion of the F1, F2, and F11 spent fuels based on the fuel element F16, which was assumed to be fresh fuel, using the NDA method.

Table 3 shows fuel content and weight percentage calculations of the U, U, and Pu isotopes from MSTR log book information based on the total power run over the by: 1.

Heavy isotope and burn-up determination in SGHWR fuel W. Fox SGHWR Development Division UKAEA Winfrith 85 90 Introduction The SGHWR Fuel and Lattice Array Scope of the Study Calculation Methods The Measurements The Comparison Summary Acknowledgements SYNOPSIS The irradiation history of specific fuel clusters may "be calculated in a.

The total burnup was determined by Nd and the fractional U burnup was determined by U and Pu mass spectrometric methods. The isotopic compositions of U, Pu, Nd, and Cs after their separation from the irradiated fuel samples were measured using thermal ionization mass by: 4.

Burnup is an important parameter in criticality safety evaluations of spent nuclear fuel in which burnup credit is taken into account. The Neodymium method is widely used to evaluate the burnup of post irradiation examination (PIE) samples, and it is well known for its good by: Burn-up measurement on an irradiated mixed oxide (MOX) test fuel pellet was carried out through measurements on the dissolver solution by HPLC-Thermal Ionization Mass Spectrometric (TIMS) technique.

The studies carried out using HPLC as well as TIMS for quantification of burn-up value are described. While in one case, both the separation and determination of elements of interest (U, Pu Cited by: In this work, we propose the use of APT for determining the local burnup in irradiated nuclear fuel using the quantification of U isotopes.

This is demonstrated on an as-received low-enriched (nominal ∼% U) U–7Mo fuel for enrichment uniformity and on the irradiated fuels at two different burnup levels, namely, intermediate burnup Author: Mukesh Bachhav, Jian Gan, Dennis Keiser, Jeffrey Giglio, Daniel Jädernäs, Ann Leenaers, Sven Van den.

Nuclear Fuel Burnup Records: Generation And Accuracy. Mourad Aissa, US Nuclear Regulatory Commission, Washington, DC, USA. John Wagner, Oak Ridge National Laboratory, Oak Ridge, TN, USA. CSN - IAEA International Workshop on Advances in Applications of Burnup Credit For.

Spent Fuel Storage, Transportation, Reprocessing, and Disposition. For fuel burnup determination in IRT-2M geometry of the LVR reactor, a measurement system was developed and calibrated for evaluation of a single fission product absolute activity (Koleska et al., a, Koleska et al., b).

The system was located in one of the spent fuel pools of the by: 6. The spectrometric technique has many nuclear-fuel related applications, including: Determination of burnup and power distributions of the nuclear fuel rod for code validation (Matsson et al., Highlights Gamma-ray spectroscopy was employed to measure burnup attained by MTR fuel elements.

Measurements were performed at the storage pool area of the RP research reactor. Cs was burnup monitor for fuel elements with cooling times shorter than two years. Apparatus was calibrated in efficiency to obtain absolute average burnup values.

The mean deviation between theoretical and Cited by: 8. sented in this work for the case of unknown irradiated nuclear fuel, either in bulk or particle form. The origin is determined in terms of the fuel type and its fresh composition, the reactor where it was irradiated and its final burnup.

The method is based on the U, Pu isotopic com-positions of the unknown irradiated nuclear fuel. In nuclear power technology, burnup (also known as fuel utilization) is a measure of how much energy is extracted from a primary nuclear fuel source.

It is measured both as the fraction of fuel atoms that underwent fission in %FIMA (fissions per initial metal atom) and as the actual energy released per mass. Impact of extended burnup on the nuclear fuel cycle Proceedings of an Advisory Group Meeting held in Vienna, December The use in this book of particular designations of countries or territories does not imply any Impact of extended burnup on the quality of plutonium and recycled uranium.The burnup of fuel pins in the subassemblies irradiated at the range from to %FIMA in the JOYO MK-II core were measured by the isotope dilution analysis.

namely Neodymium method.The use of uranium oxide (UOX) nuclear fuel with higher enrichments and burnups has been increasing around the world as the reliability of UOX fuel increases and the economics of moving to higher burnup fuel improves. Burnup extension affects all important stages of the nuclear fuel cycle and thus concerns the entire nuclear industry.