Determination of PuO2% in power reactor mixed oxide fuel blends (0.4–44% PuO2) by neutron well co-incidence counting technique

Karande, A. P.; Fulzele, Amardeep; Prakash, Amrit; Afzal, Md.; Panakkal, J.P.; Kamath, H.S.

doi:10.1007/s10967-010-0497-5

Cited by 12 publications

(5 citation statements)

References 2 publications

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“…The influence of 238 Pu on the results of uranium isotope ratio measurement was negligible in this work. In U-Pu mixed oxides as fuels for commercial nuclear power plants, an assumed maximum ratio of 238 Pu/ 238 U in the fuels is estimated to be approximately 0.04 (Aggarwal et al, 2007;Karande et al, 2010), which is 20 times larger than those of the samples measured in this work. Typical signal profiles of m/z 238 in the particles with the U/Pu ratios of 1, 10, and 70 are shown in Fig.…”

Section: Resultsmentioning

confidence: 56%

Direct isotope ratio analysis of individual uranium–plutonium mixed particles with various U/Pu ratios by thermal ionization mass spectrometry

Suzuki

Esaka

Miyamoto

et al. 2015

Applied Radiation and Isotopes

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Section: Resultsmentioning

confidence: 56%

Direct isotope ratio analysis of individual uranium–plutonium mixed particles with various U/Pu ratios by thermal ionization mass spectrometry

Suzuki

Esaka

Miyamoto

et al. 2015

Applied Radiation and Isotopes

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“…It is desirable to have a process contro assay technique using Neutron Well Coinc composition (Fig.3) and is being used at Adva MOX fuel for reactors in India [5]. …”

Section: Mixed Powdermentioning

confidence: 99%

Techniques for Assuring the Integrity of Fuel Pins for Fast Reactors

Panakkal

2014

Procedia Engineering

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The integrity of the nuclear fuel pins is of paramount importance from the point of view of safe and efficient operation of nuclear reactors. The fissile fuel pellets are loaded in thin clad tubes and closed by welding of end plugs at both the ends. The integrity of the final fuel pin fabricated is ensured by employing a number of techniques, both destructive and non-destructive at different stages of fabrication. The specifications of the raw materials used, intermediate products and the final product are very carefully made by the designers in consultation with the manufacturers and quality control personnel. The starting feed materials used for fabricating the hardware viz .clad tubes, end plugs, spacer wire and spring are subjected to rigorous quality control checks so that the products meet the design criteria and withstand safely the operating conditions. The material, dimensions, physical, mechanical and chemical characteristics of the clad material are specified considering the time to be spent by the fuel pin in the reactor and the adverse conditions like radiation, temperature, pressure to which the fuel pin is subjected. A number of quality control checks are carried out to assure that the hardware meet the required parameters.Uranium -Plutonium mixed oxide (MOX), enriched Uranium dioxide fuel, Plutonium -Uranium Carbide (MC) pellets are commonly used as fuel for fast reactors. MOX fuel is made from a mixture of Uranium dioxide and Plutonium dioxide as the starting material. The specifications of initial powders, blended powder, green pellets and sintered pellets are carefully drawn so that the integrity of the fuel pin is not endangered in the reactor. A number of non-destructive evaluation techniques have been devised and adopted at Bhabha Atomic Research Centre during the manufacture of MOX and MC pellets for Prototype Fast Breeder Reactor (PFBR) and Fast Breeder Test Reactor (FBTR). The accepted fuel pellets are encapsulated in first end plug welded tubes after degassing. The integrity of the welding of the end plugs depends on the welding procedures adopted. The evaluation techniques should be chosen such that the quality of the welds is ensured. The strength, penetration, freedom from defects, leak tightness, dimensions and color are the major parameters checked. The welds are subjected to a number of checks before wire wrapping. The quality of wire wrap welds is also ensured by suitable methods.The fuel pins are subjected to metrological inspection ( length, diameter, bow). Even though the fuel pins are fabricated as per the approved plans, the designers would still like to have a final check on the correct loading of the hardware and fuel pellets in the correct order. A number of non-destructive evaluation techniques have been developed specially for mixed oxide and mixed carbide fuel pins which ensures loading of pellets of required composition and hardware components in the correct order. Loading of pellets of wrong composition, absence of pellets or hardware and presence of wrong component a...

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“…Recently, MOXs have become a potential candidate fuel for thermal reactors as well. 2,3 Like any other nuclear fuel, MOX fuels also have to undergo very stringent quality control, during and aer their fabrication. But unlike UO 2 pellets, in MOX fuel pellets the evaluation of microhomogeneity (homogeneity at the micron level) aer their fabrication is an additional important step in the quality control of these fuels.…”

Section: Introductionmentioning

confidence: 99%

Evaluation of compositional micro-homogeneity in MOX fuels using lab based μ-XRF spectrometry

Sanyal

Kanrar

Lenka

et al. 2022

J. Anal. At. Spectrom.

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Determination of PuO2% in power reactor mixed oxide fuel blends (0.4–44% PuO2) by neutron well co-incidence counting technique

Cited by 12 publications

References 2 publications

Direct isotope ratio analysis of individual uranium–plutonium mixed particles with various U/Pu ratios by thermal ionization mass spectrometry

Direct isotope ratio analysis of individual uranium–plutonium mixed particles with various U/Pu ratios by thermal ionization mass spectrometry

Techniques for Assuring the Integrity of Fuel Pins for Fast Reactors

Evaluation of compositional micro-homogeneity in MOX fuels using lab based μ-XRF spectrometry

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