Applying the continuous-energy Monte Carlo calculation code, MVP3, to analysis of kinetic parameters measured for light-water moderated UO<sub>2</sub> and MOX cores of the TCA and EOLE critical facilities

Yamamoto, Toru; Iwahashi, Daiki; Sakai, Tomohiro

doi:10.1080/00223131.2020.1727375

Cited by 4 publications

(2 citation statements)

References 19 publications

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“…In the illustrated example (Fig. 1 d) we used the values of the 100% UO 2 compared to a 100% mixed oxide (MOX) core loading (about 8wt% of Pu) of the EOLE research reactor MISTRAL 1 and 2 programs 21 .…”

Section: Resultsmentioning

confidence: 99%

“…Taking the differences in predicted for the case example of a UO 2 and MOX core as used in Fig. 1 d, namely 1/s for UO 2 fuel and 1/s for MOX with 8wt% of Pu 21 , we find that the observation of fuel changes will require the detection of a relative change in of 4% or less. The more sensitive parameter with fuel composition is arguably the delayed neutron fraction : For a UO 2 it is around 0.0075, whilst for a full MOX core it is 0.0035.…”

Section: Discussionmentioning

confidence: 99%

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Gamma noise to non-invasively monitor nuclear research reactors

Pakari,

Mager,

Frajtag

et al. 2024

Sci Rep

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Autonomous nuclear reactor monitoring is a key aspect of the International Atomic Energy Agency’s strategy to ensure nonproliferation treaty compliance. From the rise of small modular reactor technology, decentralized nuclear reactor fleets may strain the capacities of such monitoring and requires new approaches. We demonstrate the superior capabilities of a gamma detection system to monitor the criticality of a zero power nuclear reactor from beyond typical vessel boundaries, offering a powerful alternative to neutron-based systems by providing direct information on fission chain propagation. Using the case example of the research reactor CROCUS, we demonstrate how two bismuth germanate scintillators placed outside the reactor vessel can precisely observe reactor criticality using so called noise methods and provide core status information in seconds. Our results indicate a wide range of applications due to the newly gained geometric flexibility that could find use in fields beyond nuclear safety.

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Section: Resultsmentioning

confidence: 99%

Section: Discussionmentioning

confidence: 99%

Gamma noise to non-invasively monitor nuclear research reactors

Pakari,

Mager,

Frajtag

et al. 2024

Sci Rep

View full text Add to dashboard Cite

show abstract

Trend in criticality calculation results of borated-water-moderation experimental cores relating to ¹⁰B(n, α) cross section

Yamamoto¹

2020

Journal of Nuclear Science and Technology

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Continuous-energy Monte Carlo calculation analysis of light-water moderation critical experiments with aqueous solution samples of B, Rh, Cs, Nd, Sm, Eu, Gd, and Er

Yamamoto¹

2020

Journal of Nuclear Science and Technology

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Applying the continuous-energy Monte Carlo calculation code, MVP3, to analysis of kinetic parameters measured for light-water moderated UO₂ and MOX cores of the TCA and EOLE critical facilities

Cited by 4 publications

References 19 publications

Gamma noise to non-invasively monitor nuclear research reactors

Gamma noise to non-invasively monitor nuclear research reactors

Trend in criticality calculation results of borated-water-moderation experimental cores relating to ¹⁰B(n, α) cross section

Continuous-energy Monte Carlo calculation analysis of light-water moderation critical experiments with aqueous solution samples of B, Rh, Cs, Nd, Sm, Eu, Gd, and Er

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Applying the continuous-energy Monte Carlo calculation code, MVP3, to analysis of kinetic parameters measured for light-water moderated UO2 and MOX cores of the TCA and EOLE critical facilities

Cited by 4 publications

References 19 publications

Gamma noise to non-invasively monitor nuclear research reactors

Gamma noise to non-invasively monitor nuclear research reactors

Trend in criticality calculation results of borated-water-moderation experimental cores relating to 10B(n, α) cross section

Continuous-energy Monte Carlo calculation analysis of light-water moderation critical experiments with aqueous solution samples of B, Rh, Cs, Nd, Sm, Eu, Gd, and Er

Contact Info

Product

Resources

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Applying the continuous-energy Monte Carlo calculation code, MVP3, to analysis of kinetic parameters measured for light-water moderated UO₂ and MOX cores of the TCA and EOLE critical facilities

Trend in criticality calculation results of borated-water-moderation experimental cores relating to ¹⁰B(n, α) cross section