Development of fuel cycles with new fuel with 8.9 mm external diameter for VVER-440: Preliminary assessment of operating efficiency
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A. Gagarinskiy
Abstract
Since the introduction of VVERs-440, their fuel assemblies are subject to ongoing improvements. Until now, the basic structural parameters of fuel, such as rod diameter of 9.1 mm, have never changed. This paper focuses on computational estimates of basic neutronic parameters of the fuel cycle that involves assemblies consisting of fuel rods with diameter reduced to 8.9 mm.
Kurzfassung
Seit der Einführung von WWER-440 werden ihre Brennelemente ständig weiterentwickelt. Bisher haben sich die grundlegenden strukturellen Parameter des Brennstoffs, wie z.B. der Stabdurchmesser von 9,1 mm, nie geändert. Diese Arbeit konzentriert sich auf eine rechnerische Abschätzung der grundlegenden Parameter des Brennstoffzyklus, bei denen Brennelemente mit einem auf 8.9 mm reduzierten Brennstabdurchmesser verwendet werden.
References
1 Bolobov, P. A.; Lazarenko, A. P.; Tomilov, M.Ju.: Development of the code package KASKAD for calculations of VVERs. 19th AER Symposium, 2009Suche in Google Scholar
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3 Saarinen, S.: Benefits of reducing cladding thickness from outside. FORTUM, 6th Russian-Finnish-Hungarian Scientific & Technical Seminar “Fabrication experience, operation and prospects of fuel and fuel cycle improvement for NPPs with VVER-440 reactors”, 18–19 April 2012, Espoo, FinlandSuche in Google Scholar
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© 2017, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2016
- Technical Contributions/Fachbeiträge
- Physical startup tests for VVER-1200 of Novovoronezh NPP: advanced technique and some results
- Experimental study of asymmetric boron dilution at VVER-1000 of Kudankulam NPP and its simulation
- Study on the impact of transition from 3-batch to 4-batch loading at Loviisa NPP on the long-term decay heat and activity inventory
- New engineering safety factors for Loviisa NPP core calculations
- Development of fuel cycles with new fuel with 8.9 mm external diameter for VVER-440: Preliminary assessment of operating efficiency
- Investigation of circulating temperature fluctuations of the primary coolant in order to develop an enhanced MTC estimator for VVER-440 reactors
- Recalculating the steady state conditions of the V-1000 zero-power facility at Kurchatov Institute using Monte Carlo and nodal diffusion codes
- Start-up of a cold loop in a VVER-440, the 7th AER benchmark calculation with HEXTRAN-SMABRE-PORFLO
- Verification results of methodology for determining the weighted mean coolant temperature in the primary circuit hot legs of WWER-1000 reactor plants
- Advances in HELIOS2 nuclear data library
- ANDREA 2.2 and 2.3 – Advances in modelling of VVER cores
- CFD analyses of the rod bowing effect on the subchannel outlet temperature distribution
- A methodology for the estimation of the radiological consequences of a Loss of Coolant Accident
- Neutron balance as indicator of long-term resource availability in growing nuclear energy system
- Analysis of changes in the fuel component of the cost of electricity in the transition to a closed fuel cycle in nuclear power system
- Experimental and numerical thermal-hydraulics investigation of a molten salt reactor concept core
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2016
- Technical Contributions/Fachbeiträge
- Physical startup tests for VVER-1200 of Novovoronezh NPP: advanced technique and some results
- Experimental study of asymmetric boron dilution at VVER-1000 of Kudankulam NPP and its simulation
- Study on the impact of transition from 3-batch to 4-batch loading at Loviisa NPP on the long-term decay heat and activity inventory
- New engineering safety factors for Loviisa NPP core calculations
- Development of fuel cycles with new fuel with 8.9 mm external diameter for VVER-440: Preliminary assessment of operating efficiency
- Investigation of circulating temperature fluctuations of the primary coolant in order to develop an enhanced MTC estimator for VVER-440 reactors
- Recalculating the steady state conditions of the V-1000 zero-power facility at Kurchatov Institute using Monte Carlo and nodal diffusion codes
- Start-up of a cold loop in a VVER-440, the 7th AER benchmark calculation with HEXTRAN-SMABRE-PORFLO
- Verification results of methodology for determining the weighted mean coolant temperature in the primary circuit hot legs of WWER-1000 reactor plants
- Advances in HELIOS2 nuclear data library
- ANDREA 2.2 and 2.3 – Advances in modelling of VVER cores
- CFD analyses of the rod bowing effect on the subchannel outlet temperature distribution
- A methodology for the estimation of the radiological consequences of a Loss of Coolant Accident
- Neutron balance as indicator of long-term resource availability in growing nuclear energy system
- Analysis of changes in the fuel component of the cost of electricity in the transition to a closed fuel cycle in nuclear power system
- Experimental and numerical thermal-hydraulics investigation of a molten salt reactor concept core
