Time-dependent variation of the neutron multiplication factor in spent fuel storage
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M. J. Leotlela
Abstract
After spent fuel assemblies have been discharged from the reactor, reactivity will fluctuate as the cooling period progresses because of changes in the number density of fissile nuclides and neutron absorber nuclides. The purpose of this project was (1) to quantify the contribution of each individual nuclide to the reactivity of the fissile system, (2) to identify nuclides that are responsible for the fluctuation in reactivity, and (3) to determine the effect of the number of nuclides on reactivity. This paper will present the results of the study of the behaviour of the keff with respect to variation in the duration of the cooling period during storage.
Kurzfassung
Nach dem Entladen abgebrannter Brennelemente aus einem Reaktor schwankt die Reaktivität mit fortschreitender Kühlung wegen Änderung der Teilchenzahldichte der Spaltnuklide und der Neutronenabsorbernuklide. Zweck der Untersuchungen im vorliegenden Beitrag war es, (1) den Beitrag eines jeden individuellen Radionuklids zur Reaktivität des Spaltsystems zu identifizieren, (2) Nuklide, verantwortlich für die Reaktivitätsschwankungen zu identifizieren, und (3) den Effekt der Anzahl der Nuklide auf die Reaktivität zu bestimmen. Dieser Beitrag stellt die Ergebnisse der Untersuchungen des Verhaltens von keff in Bezug auf Schwankungen bei der Abkühldauer während der Lagerung vor.
References
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© 2017, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Investigation into the impacts of distributed inlet temperature on thermal limit during LFWH event in Chinshan plant
- Experimental study on saturated boiling of two phase natural circulation under low pressure in narrow rectangular channels
- Criticality safety analysis of TK-13 cask in Bushehr nuclear power plant
- Preliminary neutronic study on Pu-based OTTO cycle pebble bed reactor
- Developing light nano-composites with improved mechanical properties for neutron shielding
- Time-dependent variation of the neutron multiplication factor in spent fuel storage
- Investigation of the thermal performance of natTe target for 124I production in the RARS cyclotron
- Ultrasonic-resonator-combined apparatus for purifying nuclear aerosol particles
- Adams-Bashforth-Moulton method with Savitzky-Golay filter to reduce reactivity fluctuations
- Application of Pareto optimization method for ontology matching in nuclear reactor domain
- Technical Note
- New finite element-based modeling of reactor core support plate failure
- The critical slab problem for pure-triplet anisotropic scattering by singular eigenfunction method
