Facilities for Neutron Capture Therapy at IRT MEPhI Nuclear Reactor

2015 ◽  
Vol 1084 ◽  
pp. 298-305 ◽  
Author(s):  
Igor N. Sheino ◽  
Vyacheslav F. Khokhlov ◽  
Pavel V. Izhevskiy ◽  
Valery K. Sakharov ◽  
Alexander A. Portnov ◽  
...  

One of the problems in developing the neutron capture therapy (NСT) of malignancies is the absence (or unavailability) of neutron sources having necessary intensity and spectrum. The first (and the only so far) experimental medical irradiation units for neutron capture therapy in Russia were created at IRT MEPhI nuclear reactor. At the exit of the tangential channel, there is a device for irradiating superficial tumors by thermal neutrons. A combined beam of thermal and epithermal neutrons that allows processing deep-lying tumors was implemented on the basis of a thermal column.

2021 ◽  
Vol 16 (1) ◽  
Author(s):  
Huifang He ◽  
Jiyuan Li ◽  
Ping Jiang ◽  
Suqing Tian ◽  
Hao Wang ◽  
...  

AbstractBoron neutron capture therapy (BNCT) was first proposed as early as 1936, and research on BNCT has progressed relatively slowly but steadily. BNCT is a potentially useful tool for cancer treatment that selectively damages cancer cells while sparing normal tissue. BNCT is based on the nuclear reaction that occurs when 10B capture low-energy thermal neutrons to yield high-linear energy transfer (LET) α particles and recoiling 7Li nuclei. A large number of 10B atoms have to be localized within the tumor cells for BNCT to be effective, and an adequate number of thermal neutrons need to be absorbed by the 10B atoms to generate lethal 10B (n, α)7Li reactions. Effective boron neutron capture therapy cannot be achieved without appropriate boron carriers. Improvement in boron delivery and the development of the best dosing paradigms for both boronophenylalanine (BPA) and sodium borocaptate (BSH) are of major importance, yet these still have not been optimized. Here, we present a review of this treatment modality from the perspectives of radiation oncology, biology, and physics. This manuscript provides a brief introduction of the mechanism of cancer-cell-selective killing by BNCT, radiobiological factors, and progress in the development of boron carriers and neutron sources as well as the results of clinical study.


2020 ◽  
pp. 159-164
Author(s):  
Yury Svistunov ◽  
Nikolai Edamenko ◽  
Vassily Gudkov ◽  
Irina Skudnova

The paper discusses dynamics of charged particles and neutrons in boron neutron capture therapy system (BNCT) as well as geometrical and physical optimization of BNCT system elements. Our choice is BNCT system with linear accelerator. BNCT track includes ion injector, RFQ, DTL, neutron-producing target and neutron moderator which provides an exit (last collimator) flux of epithermal neutrons satisfied to International Atomic Energy Agency (IAEA) requirements. The following software tools IBSimu, LIDOS, COMSOL Multiphysics and PHITS were used for modelling BNCT system.


2021 ◽  
Author(s):  
Yinghuai Zhu ◽  
Jianghong Cai ◽  
Narayan S Hosmane ◽  
Minoru Suzuki ◽  
Kazuko Uno ◽  
...  

Following the latest development and popularization of the neutron sources, boron neutron capture therapy (BNCT) has re-attracted great efforts and interest from both academia and pharmaceutical industry. The FDA approved...


1997 ◽  
Author(s):  
J. F. Harmon ◽  
R. J. Kudchadker ◽  
J. F. Kunze ◽  
S. W. Serrano ◽  
X. L. Zhou ◽  
...  

Atomic Energy ◽  
2004 ◽  
Vol 97 (3) ◽  
pp. 626-631
Author(s):  
O. E. Kononov ◽  
V. N. Kononov ◽  
A. N. Solov’ev ◽  
M. V. Bokhovko

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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