Proton linear accelerator for boron-neutron capture therapy
At the present time radiotherapy, surgery and chemotherapy are the main methods of treatment of malignant tumors. They may be used individually or in combination with other methods.
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| Zitieren: | Proton linear accelerator for boron-neutron capture therapy / V.M. Sanin, V.A. Bomko, B.V. Zaitsev, A.S. Zadvorny, A.P. Kobets, Yu.P. Mazalov, Z.E. Ptukhina, B.I. Rudjak // Вопросы атомной науки и техники. — 1999. — № 4. — С. 96-97. — Бібліогр.: 5 назв. — англ. |
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irk-123456789-815062015-05-18T03:02:28Z Proton linear accelerator for boron-neutron capture therapy Sanin, V.M. Bomko, V.A. Zaitsev, B.V. Zadvorny, A.S. Kobets, A.P. Mazalov, Yu.P. Ptukhina, Z.E. Rudjak, B.I. At the present time radiotherapy, surgery and chemotherapy are the main methods of treatment of malignant tumors. They may be used individually or in combination with other methods. 1999 Article Proton linear accelerator for boron-neutron capture therapy / V.M. Sanin, V.A. Bomko, B.V. Zaitsev, A.S. Zadvorny, A.P. Kobets, Yu.P. Mazalov, Z.E. Ptukhina, B.I. Rudjak // Вопросы атомной науки и техники. — 1999. — № 4. — С. 96-97. — Бібліогр.: 5 назв. — англ. 1562-6016 http://dspace.nbuv.gov.ua/handle/123456789/81506 en Вопросы атомной науки и техники Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
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Digital Library of Periodicals of National Academy of Sciences of Ukraine |
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| language |
English |
| description |
At the present time radiotherapy, surgery and chemotherapy are the main methods of treatment of malignant tumors. They may be used individually or in combination with other methods. |
| format |
Article |
| author |
Sanin, V.M. Bomko, V.A. Zaitsev, B.V. Zadvorny, A.S. Kobets, A.P. Mazalov, Yu.P. Ptukhina, Z.E. Rudjak, B.I. |
| spellingShingle |
Sanin, V.M. Bomko, V.A. Zaitsev, B.V. Zadvorny, A.S. Kobets, A.P. Mazalov, Yu.P. Ptukhina, Z.E. Rudjak, B.I. Proton linear accelerator for boron-neutron capture therapy Вопросы атомной науки и техники |
| author_facet |
Sanin, V.M. Bomko, V.A. Zaitsev, B.V. Zadvorny, A.S. Kobets, A.P. Mazalov, Yu.P. Ptukhina, Z.E. Rudjak, B.I. |
| author_sort |
Sanin, V.M. |
| title |
Proton linear accelerator for boron-neutron capture therapy |
| title_short |
Proton linear accelerator for boron-neutron capture therapy |
| title_full |
Proton linear accelerator for boron-neutron capture therapy |
| title_fullStr |
Proton linear accelerator for boron-neutron capture therapy |
| title_full_unstemmed |
Proton linear accelerator for boron-neutron capture therapy |
| title_sort |
proton linear accelerator for boron-neutron capture therapy |
| publisher |
Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| publishDate |
1999 |
| url |
http://dspace.nbuv.gov.ua/handle/123456789/81506 |
| citation_txt |
Proton linear accelerator for boron-neutron capture therapy / V.M. Sanin, V.A. Bomko, B.V. Zaitsev, A.S. Zadvorny, A.P. Kobets, Yu.P. Mazalov, Z.E. Ptukhina, B.I. Rudjak // Вопросы атомной науки и техники. — 1999. — № 4. — С. 96-97. — Бібліогр.: 5 назв. — англ. |
| series |
Вопросы атомной науки и техники |
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PROTON LINEAR ACCELERATOR FOR BORON-NEUTRON CAPTURE
THERAPY
V.M.Sanin, V.A.Bomko, B.V.Zaitsev, A.S. Zadvorny, A.P.Kobets, Yu.P.Mazalov, Z.E.Ptukhina,
B.I.Rudjak
NSC KIPT, Kharkov, Ukraine
At the present time radiotherapy, surgery and
chemotherapy are the main methods of treatment of
malignant tumors. They may be used individually or in
combination with other methods. The main
disadvantage of the traditional methods of radiotherapy
is the fact that ionizing radiation damages not only
malignant cells but also surrounding healthy tissues.
There are also tumors resistive to most extensively used
gamma-radiation and malignant new formations like
multiform glioblastoma (badly localized form of the
brain tumor with plenty of branches) and melanoma
(aggressive form of the skin cancer) which are
practically incurable and cause the death of about a
million people a year. Currently methods of treatment of
malignant tumors with ions accelerated to high energies,
and neutron methods directed to decrease the harmful
effect on healthy tissues, are developed in the world.
In theory the ideal method of radiotherapy may
be the method in which only cancer cells are
disintegrated, and healthy cells are not affected. The
method of boron-neutron-capture therapy (BNCT),
which is essentially a binary radiation method, satisfies
this ideal best. In BNCT method the source of strong
ionizing short-range radiation is in the cancer cells. This
radiation is generated as a result of interaction between
external thermal neutron field and atoms of 10B (stable
isotope), with which cancer cells are saturated
previously. In the reaction 10B(n,á)7Li two short-range
ions (helium and lithium) are generated which
disintegrate the cancer cell (Fig.1).
10B γ
Cancer cell
4He (path length
∼9µm)
7Li (path length
∼6µm)
n
(thermal)
∼10µm
Fig.1.
In this reaction the lithium ion may occur both in
the ground state, and in the excited state with emitting γ-
quanta:
10B + nth 7Li* (0.84 МeV) + 4He (1.47 МeV) +
γ (0.48 МeV) 93.7%
10B + nth 7Li (1.01 МэВ) + 4He (1.78 МэВ) 6.3%
Path lengths of lithium and helium ions do not
exceed the average size of a cell. Therefore, only cells
containing boron atoms are affected. Boron atoms are
injected to the tumor by pharmacological boron-
containing preparations capable of accumulating only in
cancer cells. The boron concentration in the tumor of
about 30ìgm/gm and neutron flux of about 109 n/cm2 is
necessary for adequate therapy. The cross-section of the
mentioned reaction on 10B nucleus is thousands times
higher than cross-sections of 14N(n,p)14C and 1H(n,ã)2H
undesirable reactions on nitrogen and hydrogen that
tissues contain.
Hence the BNCT method may be used for
treatment of badly localized aggressive forms of tumors
including above mentioned. Selective pharmacological
preparations find cancer cells and deliver boron there.
The neutrons interact with boron containing cells and
destroy them.
The progress of the BNCT method is determined
by the achievements in the field of creation of the boron
containing preparations and in creation of the neutron
sources with the required parameters. Investigations of
the BNCT method have shown that the irradiation
immediately by thermal neutrons is not efficient
because of their small penetrability. The best procedure
considers an irradiation by epithermal neutrons with
energies of 0.5eV up to 10 KeV, which better penetrate
through osseous and soft tissues and thermalize as they
penetrate through these tissues before reaching the
tumor.
At the present time most of neutron sources for
medical investigations of the BNCT method are based
on the nuclear reactors. Such investigations are being
carried out at the Brookhaven Medical Research
Reactor (BMRR), at the Gorgia reactor (GTRR), at the
Massachusetts Institute of Technology Reactor (MITR),
at the National engineer laboratory in Idaho (INEL), at
the PBF reactor in Patten (Netherlands), and so on.
To obtain a beam with appropriate spectral
neutron characteristics, with a minimal contamination
by gamma-radiation, thermal and fast neutrons, the
output devices of these sources are equipped with
special moderators, reflectors and absorbers. It is
complicated and frequently expensive devices.
The sources of fast neutrons based on proton
accelerators are suggested, which also require
complicated output devices and high beam powers (tens
and even hundreds kilowatt) [1].
Recently a new version of the neutron source
was suggested based on proton accelerator with energy
of 2 MeV possessing a number of advantages in
comparison with reactor–based sources [2-4]. It was
suggested to use 7Li(p,n)7Be reaction near the threshold
for neutron generation. The threshold proton energy in
this reaction is 1.881 MeV. Despite the fact that cross
sections of the reaction near the threshold are low, such
approach possesses some positive properties, which
compensate partly this disadvantage. Energies of the
generated neutrons in the threshold region are close to
epithermal that simplifies considerably the problem of
moderating and allows us to do it without complicated
output devices. The neutron flux from the lithium target
is kinematically collimated and irradiated object may be
located in several centimeters from the source that
increases efficiency of use of a neutron beam. The
ВОПРОСЫ АТОМНОЙ НАУКИ И ТЕХНИКИ. 1999. № 4.
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96
neutron flux is directed to a forward hemisphere and
radiation protection is considerably simplified in
comparison with that of the reactor version. The proton
accelerator for this purpose is compact, simple and
inexpensive in operation and may be installed
immediately in hospitals. This condition also is
important because the number of nuclear reactors
suitable for BNCT all over the world is limited and
cannot satisfy with need all requiring in treatment by
this method. Development and creation of such
accelerators do not require further development of
physics and technology of accelerators.
At the University in Idaho the investigations of
neutron sources for BNCT are being carried out on a
linear accelerator with RF quadruple focusing (RFQ)
and on a proton electrostatic accelerator with energy of
2 MeV [5]. The investigations have shown that for
BNCT based on these accelerators, the proton currents
of 3 –5 mA are necessary. Under this condition the
neutron fluence of 5x1012 n/cm2 is achieved with total
doze per hour of 2000cGy on a tumor containing 30 µ
gm/gm of 10B, what is necessary for therapy and is
tolerant for normal tissues. A special lithium target with
the cooling system is necessary for removal of a heat
power of 6-10kW. The experimental results and
mathematical calculations have shown that this source
can produce neutron beam for BNCT at proton energies
of 1.91 MeV with the intensity and nominal overall
effectiveness of those available at research reactors, and
with lower thermal deposition than in conventional
accelerator based designs.
We propose to create a proton linear accelerator
for the BNCT method based on the existing at NSC
KPTI linear accelerator of multicharge ions (MILAC)
analogous to that in Idaho. It is supposed to create a new
accelerating section for energy of 2 MeV with
alternating phase focusing (APF) and moving bunch
center that provides considerable capture both in radial,
and in longitudinal motion. At the first stage it is
assumed to create an accelerator with the proton current
of 1-2 mA. Further it will be increased to 5 mA. For
creation of such accelerator most of the existing
equipment of MILAC accelerator could be used: RF
equipment, vacuum system, the basic part of the
injector, control system, working areas. The choice of
such scheme of the accelerator is stipulated by large rate
of acceleration, availability of the ready equipment,
experience in development and creation of such
systems, simplicity of manufacturing, greater
compactness in a comparison with RFQ systems, and
also existing industrial basis.
The common view of BNCT circuit is shown on
Fig.2.
Proton accelerator
Cooled lithium
target
Moderator
Ep=1.91 MeV
Reflector
Fig.2. The common view of BNCT circuit.
At the present time in the Ukraine there are no
neutron sources suitable for the BNCT method. The
proposed neutron source could be constructed in the
short time with the minimal financial contribution, and
to supply beginning of investigations in this field. The
evaluations show that it can be created during about two
years, and financial contribution of $ 100,000 is
necessary for this purpose. At the present time
Ukrainian medical researchers are taking an active
interest to the BNCT method which was accepted as the
most promising in treatment of malignant diseases,
especially above mentioned. There is a number of large
medical institutions interested in development of this
method, and are ready for cooperation in this area.
Creations of a neutron source will need some
modernizing of existing systems, creation of new
accelerating section, target device with a system of
cooling and creation of radiation protection.
The parameters of a designed proton accelerator
are shown in table.
Table
Main parameters of linear proton accelerator for BNCT
The name of a parameter and unit
1 Input energy of ions, keV 150
2 Output energy of ions, keV 1910
3 Mass-to-charge ratio, À/q 1
4 Operating frequency ÌHz 150
5 Electric field in gaps, MV/m 8
6 Aperture of drift tubes, mm 16-26
7 Length of accelerating structure, m 1.2
8 Number of drift tubes 12
9 Number of focusing regions 3
10 Number of bunching regions 4
11 Radial acceptance π mm mrad 2
12 Longitudinal capture, deg. 150
13 Energy spread (for ∆Win.=1%) % 1.5
14 Longitudinal of output bunch deg 30
15 Pulse RF power kW 200
16 Duty factor % 2.5
17 Average beam current mA 1-2
REFERENCES
1. C.K. Wang, T.E. Blue and R. Gahbauer, "A
Neutronic Study of an Accelerator based Neutron
Irradiation Facility for Boron Neutron Capture
Therapy", Nuclear Technology, 84, 93, 1989.
2. V.N. Kononov et al., " Accelerator based Neutron
Sources Application for Neutron Capture Therapy",
Proc. 2nd All-Union Symp. on the Use of Charge
Particle Accelerators in the National Economy,
Leningrad, SU, October 1-3, 1975, Leningrad,
Efremov Inst. of Electrophysical Apparatus, v.2,
pp.60-68(1976) (in Russian).
3. V.N. Kononov et al., "Absolute Yield and Spectrum
of Neutrons from 7Li(p,n)7Be Reaction", Atomnaya
Energia, 43, p.303-305, (1977). (In English: Sov. At.
Energy, 43, 947, 1977).
4. V.N. Kononov et al., "7Li(p,n)7Be Reaction Near
Threshold: the Prospective Neutron Source for
BNCT", Proc. 1st Int. Workshop on Accelerator
based Neutron Sources for BNCT, Jackson, USA,
September 11-14, 1994, CONF-94096, v.2, pp.447-
483, (1994).
ВОПРОСЫ АТОМНОЙ НАУКИ И ТЕХНИКИ. 1999. № 4.
Серия: Ядерно-физические исследования (35), с. 96-97.
96
5. R.J. Kudchadker, F. Harmon, et al. "An Accelerator
based Epithermal Neutron Source for BNCT", 6th
Int. Conference on Nuclear Engineering, ICONE -
6451, May 10-15, 1998.
ВОПРОСЫ АТОМНОЙ НАУКИ И ТЕХНИКИ. 1999. № 4.
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