Results 151 to 160 of about 554 (180)

KLK7 overexpression promotes an aggressive phenotype and facilitates peritoneal dissemination in colorectal cancer cells

FEBS Open Bio, EarlyView.
KLK7, a tissue kallikrein‐related peptidase, is elevated in advanced colorectal cancer and associated with shorter survival. High KLK7 levels in ascites correlate with peritoneal metastasis. In mice, KLK7 overexpression increases metastasis. In vitro, KLK7 enhances cancer cell proliferation, migration, adhesion, and spheroid formation, driving ...
Yosr Z. Haffani, Tobias Dreyer, Meriem Naim, Rea Lo Dico, Natalia A. Ignatenko, Viktor Magdolen, Dalila Darmoul   +6 more
wiley   +1 more source

Chemical and engineering bases for green H₂O₂ production and related oxidation and ammoximation of olefins and analogues. [PDF]

Natl Sci Rev
Qiao M, Zhou X, Du Z, Wu P, Zong B.
europepmc   +1 more source

Breaking Stiffness-Tunability Trade-offs in Metamaterials: a Minimal Surface Guided Hybrid Lattice Strategy. [PDF]

Adv Sci (Weinh)
Zhang M, Gao K, Liu J, Zou Z, Yang J, Qian M, Zhai W, Wu Z.   +7 more
europepmc   +1 more source

Weakening the Mn-O-Si Interaction via Carbon Intercalation for the Enhanced Catalytic Ozonation of Refractory Pollutants in Environmental Matrices. [PDF]

ACS Appl Mater Interfaces
Huang H, Li W, Chen X, Yang Z, Chen M, Zhang A, He C, Tian S.   +7 more
europepmc   +1 more source

Self-Driving Laboratories for Chemistry and Materials Science. [PDF]

Chem Rev
Tom G, Schmid SP, Baird SG, Cao Y, Darvish K, Hao H, Lo S, Pablo-García S, Rajaonson EM, Skreta M, Yoshikawa N, Corapi S, Akkoc GD, Strieth-Kalthoff F, Seifrid M, Aspuru-Guzik A.   +15 more
europepmc   +1 more source

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Criticality benchmark of Monte Carlo code MCS for light water reactor fuel in transportation and storage packages

Annals of Nuclear Energy, 2021
Abstract This paper presents a verification and validation (V&V) study of the Monte Carlo neutron transport code MCS for the criticality analysis of LWR fuel in transportation and storage casks/packages. A total of 173 critical experiments from the NUREG/CR-6361 report are analyzed with MCS and the ENDF/B-VII.1 cross section library.
Lee, Hochul, Jang, Jaerim, Jang, Junkyung, Kang, Hyunwook, Kim, Wonkyeong, Lee, Deokjung, Lee, Hyun Chul   +6 more
openaire   +2 more sources

Design study of a tritium transport package for future fusion reactors

Fusion Engineering and Design, 1999
Abstract The first design of a tritium transport package with large capacity and compact size, which can be applicable to tritium transport for International Thermonuclear Experimental Reactor (ITER) was developed. To verify that the package complies with the requirements for the BU type package stipulated in the IAEA regulation of transport packages,
S. O’hira, T. Suzuki, S. Hode, M. Nishi   +3 more
openaire   +1 more source

Mechanical and Thermal Assessment by BAM of a New Package Design for the Transport of SNF From a German Research Reactor

Volume 8: Operations, Applications, and Components, 2020
Abstract For disposal of the research reactor of the Technical University Munich FRM II a new transport and storage cask design was under approval assessment by the German authorities on the basis of International Atomic Energy Agency (IAEA) requirements.
Steffen Komann, Viktor Ballheimer, Thomas Quercetti, Robert Scheidemann, Frank Wille   +4 more
openaire   +1 more source

New approach to evaluate lattice expansion of light water reactor fuel elements on criticality safety of transport packages under impact accidents

Packaging, Transport, Storage & Security of Radioactive Material, 2010
AbstractIn order to safely transport packages containing light water reactor fuel assemblies, it is essential to maintain the fuel assemblies in a subcritical state in accidents during transport. To evaluate nuclear criticality safety, an estimator is required to determine an absolutely safe level based not only on hypothetical accidents but also on ...
M. Asami, N. Odano
openaire   +1 more source

Analytical and Numerical Evaluation of the Impact Limiters Design of a Research Reactors Spent Fuel Transportation Package Half Scale Model Under 9 M Drop Tests

Volume 7: Operations, Applications and Components, 2008
Since 2001, under the IAEA (International Atomic Energy Agency) support, some regional projects have been developed in Latin America to assess storage and transportion options for the research reactors spent fuel in the region. One of the projects tasks is the design and testing of a half scale model of a dual purpose (transportation and storage ...
Miguel Mattar Neto, Carlos A. J. Miranda, Gerson Fainer, Roge´rio P. Moura˜o   +3 more
openaire   +1 more source