In vivo evaluation of PEGylated-liposome encapsulating gadolinium complexes for gadolinium neutron capture therapy

2021 ◽  
Vol 568 ◽  
pp. 23-29
Author(s):  
Woonghee Lee ◽  
Ki-Hye Jung ◽  
Ji-Ae Park ◽  
Jung Young Kim ◽  
Yong Jin Lee ◽  
...  
1992 ◽  
Vol 3 (3) ◽  
pp. 241-247 ◽  
Author(s):  
Raymond J. Paxton ◽  
Barbara G. Beatty ◽  
Aravamuthan Varadarajan ◽  
M. Frederick Hawthorne

2015 ◽  
Vol 142 (4) ◽  
pp. 767-775 ◽  
Author(s):  
Novriana Dewi ◽  
Peng Mi ◽  
Hironobu Yanagie ◽  
Yuriko Sakurai ◽  
Yasuyuki Morishita ◽  
...  

2018 ◽  
Vol 2018 ◽  
pp. 1-9 ◽  
Author(s):  
Ki-Hye Jung ◽  
Ji-Ae Park ◽  
Jung Young Kim ◽  
Mi Hyun Kim ◽  
Seyoung Oh ◽  
...  

Gadolinium-neutron capture therapy (Gd-NCT) is based on the nuclear capture reaction that occurs when 157Gd is irradiated with low energy thermal neutrons to primarily produce gamma photons. Herein, we investigated the effect of neutron capture therapy (NCT) using a small molecular gadolinium complex, Gd-DO3A-benzothiazole (Gd-DO3A-BTA), which could be a good candidate for use as an NCT drug due to its ability to enter the intracellular nuclei of tumor cells. Furthermore, MRI images of Gd-DO3A-BTA showed a clear signal enhancement in the tumor, and the images also played a key role in planning NCT by providing accurate information on the in vivo uptake time and duration of Gd-DO3A-BTA. We injected Gd-DO3A-BTA into MDA-MB-231 breast tumor-bearing mice and irradiated the tumors with cyclotron neutrons at the maximum accumulation time (postinjection 6 h); then, we observed the size of the growing tumor for 60 days. Gd-DO3A-BTA showed good therapeutic effects of chemo-Gd-NCT for the in vivo tumor models. Simultaneously, the Gd-DO3A-BTA groups ([Gd-DO3A-BTA(+), NCT(+)]) showed a significant reduction in tumor size (p<0.05), and the inhibitory effect on tumor growth was exhibited in the following order: [Gd-DO3A-BTA(+), NCT(+)] > [Gd-DO3A-BTA(+), NCT(−)] > [Gd-DO3A-BTA(−), NCT(+)] > [Gd-DO3A-BTA(−), NCT(−)]. On day 60, the [Gd-DO3A-BTA(+), NCT(+)] and [Gd-DO3A-BTA(−), NCT(−)] groups exhibited an approximately 4.5-fold difference in tumor size. Immunohistochemistry studies demonstrated that new combinational therapy with chemo-Gd-NCT could treat breast cancer by both the inhibition of tumor cell proliferation and induction of apoptosis-related proteins, with in vivo tumor monitoring by MRI.


Molecules ◽  
2019 ◽  
Vol 24 (19) ◽  
pp. 3609 ◽  
Author(s):  
Pulagam ◽  
Gona ◽  
Gómez-Vallejo ◽  
Meijer ◽  
Zilberfain ◽  
...  

Background: Boron Neutron Capture Therapy (BNCT) is a binary approach to cancer therapy that requires accumulation of boron atoms preferentially in tumour cells. This can be achieved by using nanoparticles as boron carriers and taking advantage of the enhanced permeability and retention (EPR) effect. Here, we present the preparation and characterization of size and shape-tuned gold NPs (AuNPs) stabilised with polyethylene glycol (PEG) and functionalized with the boron-rich anion cobalt bis(dicarbollide), commonly known as COSAN. The resulting NPs were radiolabelled with 124I both at the core and the shell, and were evaluated in vivo in a mouse model of human fibrosarcoma (HT1080 cells) using positron emission tomography (PET). Methods: The thiolated COSAN derivatives for subsequent attachment to the gold surface were synthesized by reaction of COSAN with tetrahydropyran (THP) followed by ring opening using potassium thioacetate (KSAc). Iodination on one of the boron atoms of the cluster was also carried out to enable subsequent radiolabelling of the boron cage. AuNPs grafted with mPEG-SH (5 Kda) and thiolated COSAN were prepared by ligand displacement. Radiolabelling was carried out both at the shell (isotopic exchange) and at the core (anionic absorption) of the NPs using 124I to enable PET imaging. Results: Stable gold nanoparticles simultaneously functionalised with PEG and COSAN (PEG-AuNPs@[4]−) with hydrodynamic diameter of 37.8 ± 0.5 nm, core diameter of 19.2 ± 1.4 nm and ξ-potential of −18.0 ± 0.7 mV were obtained. The presence of the COSAN on the surface of the NPs was confirmed by Raman Spectroscopy and UV-Vis spectrophotometry. PEG-AuNPs@[4]− could be efficiently labelled with 124I both at the core and the shell. Biodistribution studies in a xenograft mouse model of human fibrosarcoma showed major accumulation in liver, lungs and spleen, and poor accumulation in the tumour. The dual labelling approach confirmed the in vivo stability of the PEG-AuNPs@[4]−. Conclusions: PEG stabilized, COSAN-functionalised AuNPs could be synthesized, radiolabelled and evaluated in vivo using PET. The low tumour accumulation in the animal model assayed points to the need of tuning the size and geometry of the gold core for future studies.


Author(s):  
Akira Matsumura ◽  
Yasushi Shibata ◽  
Tetsuya Yamamoto ◽  
Fumiyo Yoshida ◽  
Kei Nakai ◽  
...  

RSC Advances ◽  
2020 ◽  
Vol 10 (2) ◽  
pp. 865-874 ◽  
Author(s):  
Son Long Ho ◽  
Garam Choi ◽  
Huan Yue ◽  
Hee-Kyung Kim ◽  
Ki-Hye Jung ◽  
...  

A cancer growth suppression was observed due to the GdNCT effects of the RGD-PAA-UGNPs.


ChemInform ◽  
1988 ◽  
Vol 19 (8) ◽  
Author(s):  
D. GABEL ◽  
R. G. FAIRCHILD ◽  
M. HILLMAN ◽  
G. OENBRINK ◽  
R. MUELLER

2018 ◽  
Vol 35 (3) ◽  
pp. 213-216
Author(s):  
Atika Maysaroh ◽  
Kusminarto Kusminarto ◽  
Dwi Satya Palupi ◽  
Yohannes Sardjono

Cancer is one of the leading causes of death globally, with lung cancer being among the most prevalent. Boron Neutron Capture Therapy (BNCT) is a cancer therapy method that uses the interaction between thermal neutrons and boron-10 which produces a decaying boron-11 particle and emits alpha, lithium 7 and gamma particles. A study was carried out to model an in vivo experiment of rat organisms that have lung cancer. Dimensions of a rat’s body were used in Konijnenberg research. Modeling lung cancer type, non-small cell lung cancer, was used in Monte Carlo N Particle-X. Lung cancer was modeled with a spherical geometry consisting of 3 dimensions: PTV, GTV, and CTV. In this case, the neutron source was from the radial piercing beam port of Kartini Reactor, Yogyakarta. The variation of boron concentration was 20, 25, 30, 35, 40, and 40 µg/g cancer. The output of the MCNP calculation was neutron scattering dose, gamma-ray dose and neutron flux from the reactor. A neutron flux was used to calculate the alpha proton and gamma-ray dose from the interaction of tissue material and thermal neutrons. The total dose was calculated from a four-dose component in BNCT. The results showed that the dose rate will increase when the boron concentration is higher, whereas irradiating time will decrease.


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