Experience with MTR fuel at the HOR reactor
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Abstract
In the last three years 3 events were observed in which the release rate of fission products from the fuel plates into the pool water increased significantly. Although intervention levels laid down in the permit and safety analysis were never reached, the ALARA principle was the incentive to analyse the situation and take appropriate actions.
Kurzfassung
In den letzten 3 Jahren hat es am HOR drei Zwischenfälle gegeben mit signifikant erhöhter Freisetzung von Spaltprodukten aus Brennelementplatten ins Beckenwasser. Wenn auch die Interventionswerte, wie sie in den Betriebsspezifikationen und in der Sicherheitsanalyse festgelegt sind nie erreicht wurden, war das ALARA Prinzip Anlassgenug die Lage zu analysieren und geeignete Maßnahmen zu treffen.
References
1 CERCA, Proces verbal de controle, C.I. 3090, Designation DELFT STD, No. de plan: SMR 230586F2d, No. Element: D12, 14 April1972.Search in Google Scholar
2 CERCA, Inspection records, HOR Standard Fuel Element E01 to E10, Ref.: CQ/91 509/cg/bb, Romans, 3 October1991.Search in Google Scholar
3 Hammer, J; Chawla, R; Christen, R.; Duthaler, K.: Online coolant gamma spectroscopy for detecting small fuel elements defects in the SAPHIR reactor. Proc. Int. Symp. On Research Reactor Safety, Operations and Modifications, Chalk River, Ontario, Canada, 2327 October1989, IAEASM310/60P.Search in Google Scholar
© 2004, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Improved Dancoff factors for cluster fuel bundles by the WIMSD code
- The impact of non-optimized operation of nuclear power plants on the nuclear fuel burn-up
- Experience with MTR fuel at the HOR reactor
- Comparison of two modern approaches for MBDA calculations of RBMK-type reactors
- Calculation of the energy deposition in the targets from C to U irradiated with intermediate energy protons
- U-Pb accelerator-driven sub-critical systems research at the proton beam of the JINR NUCLOTRON
- Steady state thermal-hydraulic analysis for the ETRR-2 Research Reactor
- Monte Carlo simulation of the ETRR-2 research reactor using the MCNP Code
- Preliminary evaluation of the fixed and fluidized bed nuclear reactor concept using the IAEA-INPRO methodology
- Technical Notes/Technische Mitteilungen
- A clean nuclear blasting technique for the excavation of a new isthmus canal in Central America
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Improved Dancoff factors for cluster fuel bundles by the WIMSD code
- The impact of non-optimized operation of nuclear power plants on the nuclear fuel burn-up
- Experience with MTR fuel at the HOR reactor
- Comparison of two modern approaches for MBDA calculations of RBMK-type reactors
- Calculation of the energy deposition in the targets from C to U irradiated with intermediate energy protons
- U-Pb accelerator-driven sub-critical systems research at the proton beam of the JINR NUCLOTRON
- Steady state thermal-hydraulic analysis for the ETRR-2 Research Reactor
- Monte Carlo simulation of the ETRR-2 research reactor using the MCNP Code
- Preliminary evaluation of the fixed and fluidized bed nuclear reactor concept using the IAEA-INPRO methodology
- Technical Notes/Technische Mitteilungen
- A clean nuclear blasting technique for the excavation of a new isthmus canal in Central America
