Acoustic sensor for in-pile fuel rod fission gas release measurement

2009 ◽  
Author(s):  
D. Fourmentel ◽  
JF. Villard ◽  
JY. Ferrandis ◽  
F. Augereau ◽  
E. Rosenkrantz ◽  
...  
Keyword(s):  
Acoustic Sensor ◽  
Gas Release ◽  
Fuel Rod ◽  
Fission Gas ◽  
Fission Gas Release

Acoustic Sensor for In-Pile Fuel Rod Fission Gas Release Measurement

2011 ◽  
Vol 58 (1) ◽  
pp. 151-155 ◽  
Author(s):  
D. Fourmentel ◽  
J. F. Villard ◽  
J. Y. Ferrandis ◽  
F. Augereau ◽  
E. Rosenkrantz ◽  
...  
Keyword(s):  
Acoustic Sensor ◽  
Gas Release ◽  
Fuel Rod ◽  
Fission Gas ◽  
Fission Gas Release

Axial Fission Gas Transport in Nuclear Fuel Rods

2009 ◽  
Vol 283-286 ◽  
pp. 262-267
Author(s):  
M.T. del Barrio ◽  
Luisen E. Herranz
Keyword(s):  
Nuclear Fuel ◽  
Gas Transport ◽  
Fuel Pellet ◽  
Gas Release ◽  
Gas Mixing ◽  
Fuel Performance ◽  
Fuel Rods ◽  
Fuel Rod ◽  
Fission Gas ◽  
Fission Gas Release

Fission of fissile uranium or plutonium nucleus in nuclear fuel results in fission products. A small fraction of them are volatile and can migrate under the effect of concentration gradients to the grain boundaries of the fuel pellet. Eventually, some fission gases are released to the rod void volumes by a thermally activated process. Local transients of power generation could distort even further the already non-uniform axial power and fission gas concentration profiles in fuel rods. Most of the current fuel rod performance codes neglects these gradients and the resulting axial fission gas transport (i.e., gas mixing is considered instantaneous). Experimental evidences, however, highlight axial gas mixing as a real time-dependent process. The thermal feedback between fission gas release, gap composition and fuel temperature, make the “prompt mixing assumption” in fuel performance codes a key point to investigate due to its potential safety implications. This paper discusses the possible scenarios where axial transport can become significant. Once the scenarios are well characterized, the available database is explored and the reported models are reviewed to highlight their major advantages and shortcomings. The convection-diffusion approach is adopted to simulate the axial transport by decoupling both motion mechanisms (i.e., convection transport assumed to be instantaneous) and a stand-alone code has been developed. By using this code together with FRAPCON-3, a prospective calculation of the potential impact of axial mixing is conducted. The results show that under specific but feasible conditions, the assumption of “prompt axial mixing” could result in temperature underestimates for long periods of time. Given the coupling between fuel rod thermal state and fission gas release to the gap, fuel performance codes predictions could deviate non-conservatively. This work is framed within the CSN-CIEMAT agreement on “Thermo-Mechanical Behaviour of the Nuclear Fuel at High Burnup”.

scholarly journals Design of an acoustic sensor for fission gas release characterization devoted to JHR environment measurements

2021 ◽  
Vol 253 ◽  
pp. 04028
Author(s):  
F. Baudry ◽  
E. Rosenkrantz ◽  
P. Combette ◽  
D. Fourmentel ◽  
C. Destouches ◽  
...  
Keyword(s):  
Acoustic Waves ◽  
Piezoelectric Materials ◽  
Release Kinetics ◽  
Piezoelectric Element ◽  
Operating Conditions ◽  
Acoustic Sensor ◽  
Gas Release ◽  
Wide Range ◽  
Fission Gas ◽  
Fission Gas Release

Among numerous research projects devoted to the improvement of the nuclear fuel behaviour knowledge, the development of advanced instrumentation for in-pile experiments in Material Testing Reactor is of great interest. In the frame of JHR reactor, new requirements have arisen creating new constraints. An acoustic method was tested with success during a first experiment called REMORA 3 in 2010 and 2011, and the results were used to differentiate helium and fission gas release kinetics under transient operating conditions. This experiment was leading at OSIRIS reactor (CEA Saclay, France). The maximal temperature during the irradiation test was about 150 °C. [1], [2]. We have developed thick film transducers produced by screen-printing process. They offered a wide range of possible application for the development of acoustic sensors and piezoelectric structure for harsh temperature environment measurements [3]. We proposed a screen-printed modified Bismuth Titanate piezoelectric element on alumina substrate allowing acoustic measurements [4] for JHR environment. In this paper we will focus on the mechanical design of the new sensor. This acoustic sensor is composed of an acoustic element for generation and detection of acoustic waves propagating into a cavity filled with gaz. We will detail the choice of piezoelectric materials, the thickness of the different layers, the cavity shapes, the electrical connections, the means of assembly of the different parts. Theoretical and experimental results will be given. All that point will be discussed in terms of acoustic sensor sensitivity versus dimensional constraints, in the case of a high temperature range working.

scholarly journals IMPLEMENTATION AND VALIDATION OF A FISSION GAS RELEASE MODEL FOR CTFFUEL USING THE NEA/OECD IFPE DATABASE

2021 ◽  
Vol 247 ◽  
pp. 10018
Author(s):  
A. Abarca ◽  
M. Avramova ◽  
K. Ivanov
Keyword(s):  
Heat Transfer ◽  
Material Behavior ◽  
Gas Release ◽  
Fuel Temperature ◽  
Conductivity Equation ◽  
Neutron Kinetics ◽  
Fuel Rod ◽  
Fission Gas ◽  
Release Model ◽  
Fission Gas Release

The nuclear reactors themselves are complex systems whose responses are driven by interactions between different physics phenomena within the reactor core. Traditionally, the different physics phenomena have been analyzed separately and its interaction considered via boundary conditions or closure models. However, in parallel with the development of computational technology, multi-physics coupled simulations are being used to obtain accurate predictions thanks to the consideration of the feedback effects on the fly (on-line). In the nuclear systems the fuel temperature is an important feedback parameter used to obtain the nuclear cross sections at given conditions by the neutron kinetics codes. An accurate prediction of temperature profile within the fuel rod involve several physics such as neutron kinetics, mechanics, material behavior and properties, heat transfer, thermal-hydraulics, and even chemistry. The pellet to clad gap conductance is possibly the most important source of uncertainty in the solution of conductivity equation in the fuel rod and the fuel temperature prediction. The gap conductance depends on two effects: the pellet to gap distance and the conductivity of the gas species that fill the gap. In this research work, the authors are focused on improving of the prediction of the gap gas conductivity in CTFFuel by implementing a fission gas release model in the code. The objective of this contribution is the implementation of a transient fission gas release model in CTFFuel and its validation using the experimental data available in the OECD/NEA International Fuel Performance Experiments (IFPE) database. CTFFuel is an isolated fuel heat transfer capability within the framework of CTF code, the state-of-the-art version of the Coolant Boiling in Rod Arrays Code – Two-Fluid (COBRA-TF) sub-channel thermal-hydraulic code. The code is being jointly developed by North Carolina State University (NCSU) and Oak Ridge National Laboratory (ORNL) within the US Department of Energy (DOE) Consortium for Advanced Simulation of LWRs (CASL).

Fission Gas Release from Irradiated Uranium-Plutonium Nitride Fuel

Atomic Energy ◽  
2020 ◽  
Vol 129 (2) ◽  
pp. 103-107
Author(s):  
A. F. Grachev ◽  
L. M. Zabud’ko ◽  
M. V. Skupov ◽  
F. N. Kryukov ◽  
V. G. Teplov ◽  
...  
Keyword(s):  
Gas Release ◽  
Nitride Fuel ◽  
Fission Gas ◽  
Uranium Plutonium ◽  
Fission Gas Release

Fission gas release and swelling in uranium–plutonium mixed nitride fuels

2004 ◽  
Vol 327 (2-3) ◽  
pp. 77-87 ◽  
Author(s):  
Kosuke Tanaka ◽  
Koji Maeda ◽  
Kozo Katsuyama ◽  
Masaki Inoue ◽  
Takashi Iwai ◽  
...  
Keyword(s):  
Gas Release ◽  
Fission Gas ◽  
Nitride Fuels ◽  
Uranium Plutonium ◽  
Fission Gas Release

Pellet-Cladding Interaction of LMFBR Fuel Elements at Unsteady State: An Introduction to Computer Code ISUNE-5

1981 ◽  
Vol 103 (4) ◽  
pp. 627-636 ◽  
Author(s):  
B. M. Ma
Keyword(s):  
Reactor Core ◽  
Fatigue Cracking ◽  
Computer Code ◽  
Fuel Burnup ◽  
Fuel Pellet ◽  
Gas Release ◽  
Unsteady State ◽  
Fission Gas ◽  
Fuel Elements ◽  
Fission Gas Release

The fuel pellet-cladding interaction (PCI) of liquid-metal fast breeder reactor (LMFBR) fuel elements or fuel rods at unsteady state is analyzed and discussed based on experimental results. In the analyses, the heat generation, fuel restructuring, temperature distribution, gap conductance, irradiation swelling, irradiation creep, fuel burnup, fission gas release, fuel pellet cracking, crack healing, cladding cracking, yield failure and fracture failure of the fuel elements are taken into consideration. To improve the sintered (U,Pu)O2 fuel performance and reactor core safety at high temperature and fuel burnup, it is desirable to (a) increase and maintain the ductility of cladding material, (b) provide sufficient gap thickness and plenum space for accommodating fission gas release, (c) keep ramps-power increase rate slow and gentle, and (d) reduce the intensity and frequency of transient PCI in order to avoid intense stress fatigue cracking (SFC) and stress corrosion cracking (SCC) due to fission product compounds CsI, CdI2, Cs2Te, etc. at the inner cladding surface of the fuel elements during PCI.

The role of bubbles in fission gas release from uranium dioxide

1969 ◽  
Vol 30 (1-2) ◽  
pp. 170-178 ◽  
Author(s):  
R.M. Cornell ◽  
M.V. Speight ◽  
B.C. Masters
Keyword(s):  
Uranium Dioxide ◽  
Gas Release ◽  
Fission Gas ◽  
Fission Gas Release
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