Determination of burnup and isotope composition for spent VV�R-365 fuel

Stepanov, А. V.; Makarova, T. P.; Bibichev, B. A.; Fridkin, A. M.; Lovtsyus, A. V.; Preobrazhenskaya, L.D.; Lipovskiĭ, A. A.; Тимофеев, А. Н.

doi:10.1007/bf01121229

At Energy

1980

DOI: 10.1007/bf01121229

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Determination of burnup and isotope composition for spent VV�R-365 fuel

А. V. Stepanov¹,

T. P. Makarova²,

B. A. Bibichev³

et al.

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1982

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Cited by 7 publications

(1 citation statement)

References 2 publications

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“…Determining the reactor environment that a particular spent fuel sample experienced is critical information for non-proliferation and reactor verification. In particular, the fluence is often related to the fuel burnup and, hence, the plutonium production and grade [1]. This makes the fluence an important parameter for nonproliferation and arms reduction [2].…”

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confidence: 99%

Developing Diagnostic Tools for Low-Burnup Reactor Samples

et al. 2017

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We test common fluence diagnostics in the regime of very low burnup natural uranium reactor samples. The fluence diagnostics considered are the uranium isotopics ratios 235 U/ 238 U and 236 U/ 235 U, for which we find simple analytic formulas agree well with full reactor simulation predictions. Both ratios agree reasonably well with one another for fluences in the mid 10 19 n/cm 2 range. However, below about 10 19 n/cm 2 the concentrations of 236 U are found to be sufficiently low that the measured 236 U/ 235 U ratios become unreliable. We also derive and test diagnostics for determining sample cooling times in situations where very low burnup and very long cooling times render many standard diagnostics, such as the 241 Am/ 241 Pu ratio, impractical. We find that using several fragment ratios are necessary to detect the presence of systematic errors, such as fractionation.

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confidence: 99%

Developing Diagnostic Tools for Low-Burnup Reactor Samples

et al. 2017

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Distribution of the flux density and hardness of the neutron spectrum with height and over the cross section of the heat-generating assemblies of VV�R-365 and VV�R-440 reactors

Bibichev¹,

Maiorov²,

Sidorenko³

et al. 1982

At Energy

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Correlations for the formation of actinides in nuclear reactors

Zaritskaya¹,

Rudik²

1982

At Energy

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Determination of burnup and isotope composition for spent VV�R-365 fuel

Cited by 7 publications

References 2 publications

Developing Diagnostic Tools for Low-Burnup Reactor Samples

Developing Diagnostic Tools for Low-Burnup Reactor Samples

Distribution of the flux density and hardness of the neutron spectrum with height and over the cross section of the heat-generating assemblies of VV�R-365 and VV�R-440 reactors

Correlations for the formation of actinides in nuclear reactors

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