Fission yields data generation and benchmarks of decay heat estimation of a nuclear fuel

The definition of the thermal state of containers with spent nuclear fuel is important part of the ensuring of its safe storage during all period of storage facility operation. The this work all investigations are carried out for the storage containers of spent nuclear fuel of WWER-1000 reactors, which are operated in the Dry Spent Nuclear Fuel Storage Facility in Zaporizhska NPP. The analysis of existing investigations in the world nuclear engineering science concerning to the prediction of maximum temperatures in spent nuclear fuel storage container is carried out. The absence of studies in this field is detected and the necessity of the dependence for the maximum temperature in the storage container and temperature of cooling air on the exit of ventilation duct from variated temperatures of atmospheric air and decay heat formulation is pointed out. With usage of numerical simulation by solving of the conjugate heat transfer problems, the dependence of maximum temperatures in storage container with spent nuclear fuel from atmospheric temperature and decay heat is detected. The verification of used calculation method by comparison of measured air temperature on exit of ventilation channels and calculated temperature of cooling air was carried out. By regression analysis of numerical results of studies the dependence of ventilation air temperature from the temperature of atmospheric air and the decay heat of spent nuclear fuel was formulated. For the obtained dependence the statistical analysis was carried out and confidence interval with 95% of confidence is calculated. The obtained dependences are expediently to use under maximum temperature level estimation at specified operation conditions of spent nuclear fuel storage containers and for the control of correctness of thermal monitoring system work.

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Modeling of decay heat removal from CONSTOR RBMK-1500 casks during long-term storage of spent nuclear fuel

Energy ◽

10.1016/j.energy.2018.12.217 ◽

2019 ◽

Vol 170 ◽

pp. 978-985 ◽

Cited By ~ 3

Author(s):

R. Poškas ◽

V. Šimonis ◽

H. Jouhara ◽

P. Poškas

Keyword(s):

Nuclear Fuel ◽

Spent Nuclear Fuel ◽

Heat Removal ◽

Decay Heat ◽

Long Term Storage ◽

Term Storage

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The Testing of Recent JEF(F) Decay Data and Fission Product Yields Files for Irradiated Nuclear Fuel Decay Heat Calculations

10.1063/1.1944975 ◽

2005 ◽

Cited By ~ 1

Author(s):

R. W. Mills

Keyword(s):

Fission Product ◽

Nuclear Fuel ◽

Decay Data ◽

Product Yields ◽

Decay Heat ◽

Fission Product Yields ◽

Irradiated Nuclear Fuel

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Uncertainty quantification works relevant to fission yields and decay data

EPJ Nuclear Sciences & Technologies ◽

10.1051/epjn/2018022 ◽

2018 ◽

Vol 4 ◽

pp. 43

Author(s):

Go Chiba ◽

Shunsuke Nihira

Keyword(s):

Perturbation Theory ◽

Uncertainty Quantification ◽

Nuclear Data ◽

Code System ◽

Reactor Physics ◽

Delayed Neutrons ◽

Decay Data ◽

Decay Heat ◽

Numerical Tools ◽

Fission Yields

In the present paper, firstly, we review our previous works on uncertainty quantification (UQ) of reactor physics parameters. This consists of (1) development of numerical tools based on the depletion perturbation theory (DPT), (2) linearity of reactor physics parameters to nuclear data, (3) UQ of decay heat and its reduction, and (4) correlation between decay heat and β-delayed neutrons emission. Secondly, we show results of extensive calculations about UQ on decay heat with several different numerical conditions by the DPT-based capability of a reactor physics code system CBZ.

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Integral data assimilation of the MERCI-1 experiment for the nuclear data associated with the PWR decay heat computation

EPJ Web of Conferences ◽

10.1051/epjconf/201921107004 ◽

2019 ◽

Vol 211 ◽

pp. 07004

Author(s):

J. Huyghe ◽

C. De Saint-Jean ◽

D. Lecarpentier ◽

C. Reynard-Carette ◽

C. Vaglio-Gaudard ◽

...

Keyword(s):

Reactor Core ◽

Nuclear Data ◽

Nuclear Decay ◽

Crucial Issue ◽

Decay Heat ◽

Uncertainty Calculation ◽

Experimental Values ◽

The Impact ◽

Fission Yields ◽

Integral Data

Nuclear decay heat is a crucial issue for PWR in-core safety after reactor shutdown and back-end cycle. It is a dimensioning parameter for safety injection systems (SIS) to avoid a dewatering of the reactor core. The decay heat uncertainty needs to be controlled over the largest range of applications. The assimilation of the MERCI-1 experiment was studied to provide feedbacks on nuclear data. This experiment consisted in the measurement of the decay heat of a PWR UOX fuel sample irradiated in the OSIRIS reactor, for cooling times between 45 minutes and 42 days. More specifically, the consideration of several experimental values of MERCI-1 at different cooling times was tested. This raised issues about correlations to consider between different measurements. Besides, the impact of considering correlations between independent fission yields in covariance matrices on the decay heat uncertainty calculation and on the feedbacks on nuclear data is discussed.

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Closed Fuel Cycle and Minor Actinide Multirecycling in a Gas-Cooled Fast Reactor

Science and Technology of Nuclear Installations ◽

10.1155/2009/282365 ◽

2009 ◽

Vol 2009 ◽

pp. 1-9 ◽

Cited By ~ 2

Author(s):

W. F. G. van Rooijen ◽

J. L. Kloosterman

Keyword(s):

Nuclear Fuel ◽

Fast Reactor ◽

Fuel Cycle ◽

Fission Products ◽

Nuclear Fuel Cycle ◽

Future Research ◽

Minor Actinide ◽

Closed Fuel Cycle ◽

Decay Heat ◽

Closed Nuclear Fuel Cycle

The Generation IV International Forum has identified the Gas-Cooled Fast Reactor (GCFR) as one of the reactor concepts for future deployment. The GCFR targets sustainability, which is achieved by the use of a closed nuclear fuel cycle where only fission products are discharged to a repository; all Heavy Metal isotopes are to be recycled in the reactor. In this paper, an overview is presented of recent results obtained in the study of the closed fuel cycle and the influence of the addition of extra Minor Actinide (MA) isotopes from existing LWR stockpiles. In the presented work, up to 10% of the fuel was homogeneously replaced by an MA-mixture. The results are that addition of MA increases the potential of obtaining a closed fuel cycle. Reactivity coefficients generally decrease with increasing MA content. Addition of MA reduces the reactivity swing and allows very long irradiation intervals up to 10% FIMA with a small reactivity swing. Multirecycling studies show that a 600 MWth GCFR can transmute the MA from several PWRs. By a careful choice of the MA-fraction in the fuel, the reactivity of the fuel can be tuned to obtain a preset multiplication factor at end of cycle. Preliminary decay heat calculations show that the presence of MA in the fuel significantly increases the decay heat for time periods relevant to accidents (104–105s after shutdown). The paper ends with some recommendations for future research in this promising area of the nuclear fuel cycle.

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