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Salmonella enteritis: A Rare Cause of Adult Intussusception
Toan Pham,Domenic La Paglia,Meron Pitcher 대한대장항문학회 2017 Annals of Coloproctolgy Vol.33 No.5
Intussusception is a relatively rare condition in the adult population and is commonly secondary to a malignant process. Eight to twenty percent of cases of adult intussusception are thought to be idiopathic. In children, infection has been proven to precipitate intussusception in the absence of any other cause. We present a rare case of intussusception in a healthy adult patient secondary to salmonella infection and discuss infection as a potential explanation for a proportion of the cases of adult intussusception that are thought to be idiopathic. We recommend testing for infective causes of intussusception in adults when more common causes, such as malignancy, have been excluded.
Dynamic Amplification Factor of the ITER Diagnostic Upper Port Plug
Pak, Sunil,Udintsev, Victor,Maquet, Philippe,Pitcher, Charles Spencer,Mun-Seong Cheon,Chang Rae Seon,Hyeon Gon Lee Institute of Electrical and Electronics Engineers 2014 IEEE transactions on plasma science Vol. No.
<P>The diagnostic upper port plug in ITER is a long metal box cantilevered to the vacuum vessel port with 42 × M52 studs and nuts. The plug structure has a heavy payload at the front, such as the diagnostic first wall and the diagnostic shield module to protect the diagnostic components from plasma and neutron fluxes. This kind of structural configuration is susceptible to a resonance with the transient external load. For the upper port plug, the design-driving load is electromagnetic (EM) forces due to plasma disruptions. In this paper, the dynamic amplification factor (DAF) of the structure is calculated for such EM loads. The bolted joint at the back flange of the plug structure is also considered together with the port extension of the vacuum vessel and its influence on the dynamic behavior is investigated. The analysis results show that the bolted joint reduces the DAF as well as the natural frequency of the structure.</P>
Radwaste management aspects of the test blanket systems in ITER
van der Laan, J.G.,Canas, D.,Chaudhari, V.,Iseli, M.,Kawamura, Y.,Lee, D.W.,Petit, P.,Pitcher, C.S.,Torcy, D.,Ugolini, D.,Zhang, H. North-Holland ; Elsevier Science Ltd 2016 Fusion engineering and design Vol.109 No.1
Test Blanket Systems (TBS) will be operated in ITER in order to prepare the next steps towards fusion power generation. After the initial operation in H/He plasmas, the introduction of D and T in ITER will mark the transition to nuclear operation. The significant fusion neutron production will give rise to nuclear heating and tritium breeding in the in-vessel part of the TBS. The management of the activated and tritiated structures of the TBS from operation in ITER is described. The TBS specific features like tritium breeding and power conversion at elevated temperatures, and the use of novel materials require a dedicated approach, which could be different to that needed for the other ITER equipment.
Shuhei Yamaguchi,Nobuhiro Yamaguchi,Masaki Mito,Hiroyuki Deguchi,Peter. J. Baker,Stephen. J. Blundell,Michael. J. Pitcher,Dinah. R. Parker,Simon. J. Clarke 한국물리학회 2013 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.63 No.3
The pressure effects on the 111-type Fe-based superconductor LiFeAs were investigated throughAC susceptibility measurements and X-ray diffraction experiments, and revealed a correlation betweenthe superconducting transition temperature (Tc) and the As-Fe-As bond angle (α) ratherthan the height of As from the Fe layers (hAs). As the pressure was increased, Tc of 17 K at P =0 GPa decreased down to 10 K at P = 5.2 GPa. According to a previous report from an X-raydiffraction experiment, α changes from 101.5˚ at 0 GPa to 97.8˚ at 17 GPa. The obtained changein Tc is consistent with Lee et al.’s plot of Tc as a function of α, and from this result, we concludethat Tc will fall to zero at around α = 98˚.
Desorption dynamics of deuterium in CuCrZr alloy
Thi Nguyen, Lan Anh,Lee, Sanghwa,Noh, S.J.,Lee, S.K.,Park, M.C.,Shu, Wataru,Pitcher, Spencer,Torcy, David,Guillermain, David,Kim, Jaeyong Elsevier 2017 JOURNAL OF NUCLEAR MATERIALS Vol.496 No.-
<P><B>Abstract</B></P> <P>Desorption behavior of deuterium (D<SUB>2</SUB>) in CuCrZr alloy was investigated considering sample thickness, loading and baking temperature of deuterium followed by the ITER scopes. Cylindrical specimens of 1, 3, 5 mm thick with 4 mm diameter were exposed to deuterium at a pressure of 25 bar at 120, 240 and 350 °C for 24 h, then baked at 800 °C in a vacuum chamber maintained at a pressure lower than 10<SUP>−7</SUP> Torr. Deuterium desorption characteristics such as desorption rate and amount of deuterium in the sample were estimated by analyzing the desorption peaks monitored with a residual gas analyzer (RGA), and the trapping energy of deuterium was calculated using thermal desorption spectroscopy (TDS). Secondary ion mass spectroscopy (SIMS) results showed that deuterium atoms embedded in the sample at a depth of less than 15 μm and desorbed as low as 400 °C. All absorbed deuterium atoms in the specimen were completely retrieved by dynamic pumping at 800 °C in 15 min. The desorption rate of deuterium per unit area was inversely proportional to the increment of the thickness of the sample, and was proportional to the loading temperature. Based on the assumption that a uniform distribution of interstitial sites for deuterium follows the Femi-Dirac statistics, the result of TDS demonstrated that the CuCrZr alloy has two types of trapping energies, which were estimated to be 62 and 79 kJ/mol.</P> <P><B>Highlights</B></P> <P> <UL> <LI> Desorption behavior of deuterium in CuCrZr alloys was investigated following the ITER scopes. </LI> <LI> Deuterium was embedded in CuCrZr alloys at a depth of less than 15 μm, and can be completely retrieved in 15 min through dynamic pumping at 800 °C. </LI> <LI> Desorption rate of deuterium was inversely proportional to the increment of the thickness of the sample but proportional to the loading temperature. </LI> <LI> The trapping energies of deuterium in CuCrZr alloys were 62 and 79 kJ/mol. </LI> </UL> </P>
Final design of the generic upper port plug structure for ITER diagnostic systems
Pak, S.,Feder, R.,Giacomin, T.,Guirao, J.,Iglesias, S.,Josseaume, F.,Kalish, M.,Loesser, D.,Maquet, P.,Ordieres, J.,Panizo, M.,Pitcher, S.,Portales, M.,Proust, M.,Ronden, D.,Serikov, A.,Suarez, A.,Tan North-Holland ; Elsevier Science Ltd 2016 Fusion engineering and design Vol.102 No.-
The generic upper port plug (GUPP) structure in ITER is a 6m long metal box which deploys diagnostic components into the vacuum vessel. This structure is commonly used for all the diagnostic upper ports. The final design of the GUPP structure, which has successfully passed the final design review in 2013, is described here. The diagnostic port plug is cantilevered to the vacuum vessel with a heavy payload at the front, so called the diagnostic first wall (DFW) and the diagnostic shield module (DSM). Most of electromagnetic (EM) load (~80%) occurs in DFW/DSM. Therefore, the mounting design to transfer the EM load from DFW/DSM to the GUPP structure is challenging, which should also comply with thermal expansion and tolerance for assembly and manufacturing. Another key design parameter to be considered is the gap between the port plug and the vacuum vessel port. The gap should be large enough to accommodate the remote handling of the heavy port plug (max. 25t), the structural deflection due to external loads and machine assembly tolerance. At the same time, the gap should be minimized to stop the neutron streaming according to the ALARA (as low as reasonably achievable) principle. With these design constraints, the GUPP structure should also provide space for diagnostic integration as much as possible. This requirement has led to the single wall structure having the gun-drilled water channels inside the structure. Furthermore, intensive efforts have been made on the manufacturing study including material selection, manufacturing codes and French regulation related to nuclear equipment and safety. All these main design and manufacturing aspects are discussed in this paper, including requirements, interfaces, loads and structural assessment and maintenance.