Visualization of the Internal Water Distribution at Pemfc Using Neutron Imaging Technology: Feasibility Test at Hanaro
نویسندگان
چکیده
The polymer electrolyte membrane fuel cell (PEMFC) is one of the most promising candidates for automotive applications due to its high energy conversion efficiency and absence of chemical pollution. PEMFC usually uses hydrogen and oxygen as fuel in order to generate electricity, and heat and water are generated as byproducts during that procedure. These byproducts create several problems coupled with fluid flow, heat, and mass transfer processes. Moreover, water more seriously affects the efficiency of the PEMFC system since the proton conductivity of the membrane is highly influenced by the water content. If the water content at the membrane and channel is too low, the conductivity of proton is decreased and the efficiency is dropped. Conversely, too much water content causes flooding at the channel. The flooding impedes gas flow and also reduces the efficiency [1]. Therefore, it is necessary to visualize the channel and MEA of PEMFC to maintain the water content and distribution properly. Moreover, knowledge of the water movement and distribution in the channel and membrane of PEMFC is helpful to increase the efficiency [2,3]. However, since PEMFC is usually made of metallic parts, it is difficult to visualize it by ordinary methods, such as optical light. The neutron imaging technique is one of the radiography methods which is a visualization technique that uses the attenuation of a radio ray at its transmission through the irradiated materials. X-ray, gamma-ray, and thermal neutrons can be used as a radio ray. A thermal neutron beam is the best choice to examine the inside of the PEMFC among these because the thermal neutron beam has unique characteristics for the attenuation coefficient compared with an X-ray and gamma-ray. Fig. 1 shows the mass attenuation coefficients of various elements for thermal neutrons and X-rays [4]. The mass attenuation coefficients of an X-ray increase monotonically with the atomic number. Thus, the X-ray imaging method does not supply sufficient contrast for light elements (for example, hydrogen and its compounds) when they are surrounded by heavy elements.
منابع مشابه
Estimation of neutron and gamma dose in the MNSR research reactor
In this study, the neutron and gamma doses in the dry channel and in the internal irradiation site of the Miniature Neutron Source research reactor (MNSR) has been calculated and measured. The MNSR reactor is a light water reactor with a maximum power of 30 kW and equipped with various irradiation facilities, including five irradiated sites, five irradiation sites and a dry channel. The interna...
متن کاملInvestigation of dose distribution 252Cf Isotron brachytherapy source based on TG-43U1 protocol by Monte Carlo method.
Introduction: The commercial 252Cf sources are too large in size and clinical applications of neutron brachytherapy (NBT) are limited to a small number of intracavitary treatments of cervical cancers. Recently, under the Cooperative Research and Development Agreement (CRADA) with Isotron Inc., the Oak Ridge National Laboratory (ORNL) encapsulated a new medical 252Cf sources, c...
متن کاملExtracting Model Parameters and Paradigms from Neutron Imaging of Dead-ended Anode Operation
In a PEMFC, feeding dry hydrogen into a dead-ended anode (DEA), reduces the overall system cost, weight and volume due to reduced need for a hydrogen-grade humidification and recirculation subsystems, but requires purging to remove the accumulated water and inert gas. Although the DEA method of operation might be undesirable due to its associated high spatial variability it provides a unique pe...
متن کاملDevelopment and characteristics of the HANARO neutron irradiation facility for applications in the boron neutron capture therapy field.
The HANARO neutron irradiation facility for various applications in the boron neutron capture therapy (BNCT) field was developed, and its characteristics were investigated. In order to obtain the sufficient thermal neutron flux with a low level of contamination by fast neutrons and gamma rays, a radiation filtering method was adopted. The radiation filter was designed by using a silicon single ...
متن کاملInvestigation of dose distribution 252Cf Isotron brachytherapy source based on TG-43U1 protocol by Monte Carlo method
Introduction:The commercial 252Cf sources are too large in size and clinical applications of neutronbrachytherapy (NBT) are limited to a small number of intracavitary treatments of cervical cancers. Recently, under the Cooperative Research and Development Agreement (CRADA) with Isotron Inc., the Oak Ridge National Laboratory (ORNL) encapsulated a new medical 252Cf sources, cal...
متن کاملذخیره در منابع من
با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید
عنوان ژورنال:
دوره شماره
صفحات -
تاریخ انتشار 2006