About the possibility of using the field of the portable neutron generator for treatment of oncological diseases
The possibility of using a portable neutron generator (PNG) for the treatment of oncological diseases is being considered. It has been shown that when using PNG as a neutron source, it is possible to ensure sufficient therapeutic impact on sick cells, with minimal damage to healthy cells. It's...
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irk-123456789-1361822020-02-27T12:08:53Z About the possibility of using the field of the portable neutron generator for treatment of oncological diseases Stoyanov, A.Ph. Dovbnya, A.N. Tsymbal, V.A. Применение ускорителей в радиационных технологиях The possibility of using a portable neutron generator (PNG) for the treatment of oncological diseases is being considered. It has been shown that when using PNG as a neutron source, it is possible to ensure sufficient therapeutic impact on sick cells, with minimal damage to healthy cells. It's about applying PNG in a brachytherapy tumor. It is important to note that the presence of a narrow ion- pipe- needle allows a neutron source to be placed close to the tumor, and thus to increase therapeutic influence. Numerical estimates of the density of neutrons and the consumed dose when using PNG for brachytherapy performed, it is shown that, for a short period of time (~ 1 minute), sufficient dose of radiation for therapy is absorbed. The calculations of the neutron field and absorbed dose are accom-plished through a computer program developed by the authors based on the Monte Carlo method, designed to simulate the generation, movement, braking and absorption of neutrons. Розглядається можливість застосування портативного нейтронного генератора (ПНГ) для лікування онкологічних хвороб. Показано, що за умови застосування ПНГ в якості джерела нейтронів можна забезпечити достатній терапевтичний вплив на хворі клітини, з мінімальним ураженням здорових клітин. Мова йде про застосування ПНГ при брахітерапії пухлини. Важливо зауважити, що наявність вузького іонопровода «голки» дає можливість розташувати джерело нейтронів у безпосередній близькості до пухлини, а отже - підсилити терапевтичну дію. Виконані чисельні оцінки щільності потоку нейтронів і поглиненої дози під час застосування ПНГ у брахітерапії, показано, що протягом невеликого проміжку часу (~1 хвилини) поглинається достатня для терапії доза опромінювання. Обчислення потоку нейтронів і поглиненої дози виконано за допомогою розробленої авторами комп’ютерної програми, заснованої на методі Монте-Карло і призначеної для моделювання процесів створення, руху, гальмування та поглинання нейтронів. Рассматривается возможность применения портативного нейтронного генератора (ПНГ) для лечения он-кологических заболеваний. Показано, что при применении ПНГ в качестве источника нейтронов можно обеспечить достаточное терапевтическое воздействие на больные клетки, с минимальным повреждением здоровых клеток. Речь идет о применении ПНГ при брахитерапии опухоли. Важно отметить, что наличие узкого ионопровода «иглы» позволяет разместить источник нейтронов близко к опухоли, а следовательно, усилить терапевтическое воздействие. Выполнены численные оценки плотности потока нейтронов и поглощенной дозы при использовании ПНГ для брахитерапии, показано, что в течение небольшого промежутка времени (~1 минуты) поглощается достаточная для терапии доза излучения. Расчеты потока нейтронов и поглощенной дозы выполнены с помощью разработанной авторами компьютерной программы, основанной на применении метода Монте-Карло и предназначенной для моделирования процессов образования, движения, торможения и поглощения нейтронов. 2017 Article About the possibility of using the field of the portable neutron generator for treatment of oncological diseases / A.Ph. Stoyanov, А.N. Dovbnya, V.А. Tsymbal // Вопросы атомной науки и техники. — 2017. — № 6. — С. 172-174. — Бібліогр.: 9 назв. — англ. 1562-6016 PACS: 29.25.Dz http://dspace.nbuv.gov.ua/handle/123456789/136182 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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Применение ускорителей в радиационных технологиях Применение ускорителей в радиационных технологиях |
| spellingShingle |
Применение ускорителей в радиационных технологиях Применение ускорителей в радиационных технологиях Stoyanov, A.Ph. Dovbnya, A.N. Tsymbal, V.A. About the possibility of using the field of the portable neutron generator for treatment of oncological diseases Вопросы атомной науки и техники |
| description |
The possibility of using a portable neutron generator (PNG) for the treatment of oncological diseases is being considered. It has been shown that when using PNG as a neutron source, it is possible to ensure sufficient therapeutic impact on sick cells, with minimal damage to healthy cells. It's about applying PNG in a brachytherapy tumor. It is important to note that the presence of a narrow ion- pipe- needle allows a neutron source to be placed close to the tumor, and thus to increase therapeutic influence. Numerical estimates of the density of neutrons and the consumed dose when using PNG for brachytherapy performed, it is shown that, for a short period of time (~ 1 minute), sufficient dose of radiation for therapy is absorbed. The calculations of the neutron field and absorbed dose are accom-plished through a computer program developed by the authors based on the Monte Carlo method, designed to simulate the generation, movement, braking and absorption of neutrons. |
| format |
Article |
| author |
Stoyanov, A.Ph. Dovbnya, A.N. Tsymbal, V.A. |
| author_facet |
Stoyanov, A.Ph. Dovbnya, A.N. Tsymbal, V.A. |
| author_sort |
Stoyanov, A.Ph. |
| title |
About the possibility of using the field of the portable neutron generator for treatment of oncological diseases |
| title_short |
About the possibility of using the field of the portable neutron generator for treatment of oncological diseases |
| title_full |
About the possibility of using the field of the portable neutron generator for treatment of oncological diseases |
| title_fullStr |
About the possibility of using the field of the portable neutron generator for treatment of oncological diseases |
| title_full_unstemmed |
About the possibility of using the field of the portable neutron generator for treatment of oncological diseases |
| title_sort |
about the possibility of using the field of the portable neutron generator for treatment of oncological diseases |
| publisher |
Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| publishDate |
2017 |
| topic_facet |
Применение ускорителей в радиационных технологиях |
| url |
http://dspace.nbuv.gov.ua/handle/123456789/136182 |
| citation_txt |
About the possibility of using the field of the portable neutron generator for treatment of oncological diseases / A.Ph. Stoyanov, А.N. Dovbnya, V.А. Tsymbal // Вопросы атомной науки и техники. — 2017. — № 6. — С. 172-174. — Бібліогр.: 9 назв. — англ. |
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Вопросы атомной науки и техники |
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ISSN 1562-6016. ВАНТ. 2017. №6(112) 172
ABOUT THE POSSIBILITY OF USING THE FIELD OF THE PORTABLE
NEUTRON GENERATOR FOR TREATMENT OF ONCOLOGICAL
DISEASES
A.Ph. Stoyanov, А.N. Dovbnya, V.А. Tsymbal
National Science Center “Kharkov Institute of Physics and Technology”, Kharkov, Ukraine
E-mail: wind@kipt.kharkov.ua
The possibility of using a portable neutron generator (PNG) for the treatment of oncological diseases is being
considered. It has been shown that when using PNG as a neutron source, it is possible to ensure sufficient therapeu-
tic impact on sick cells, with minimal damage to healthy cells. It's about applying PNG in a brachytherapy tumor. It
is important to note that the presence of a narrow ion- pipe- needle allows a neutron source to be placed close to the
tumor, and thus to increase therapeutic influence. Numerical estimates of the density of neutrons and the consumed
dose when using PNG for brachytherapy performed, it is shown that, for a short period of time (~ 1 minute), suffi-
cient dose of radiation for therapy is absorbed. The calculations of the neutron field and absorbed dose are accom-
plished through a computer program developed by the authors based on the Monte Carlo method, designed to simu-
late the generation, movement, braking and absorption of neutrons.
PACS: 29.25.Dz
MAIN CHARACTERISTICS OF PNG
The development of reliable and inexpensive neu-
tron sources is an urgent task, the solution of which is
necessary, first of all, for the use of such sources in ra-
diation medicine. Work in this field has been carried out
in the world for a long time [1 - 7].
The portable neutron generator (PNG) was devel-
oped at the NSC KIPT within STSU R497 project, the
yield of neutrons provided by PNG is ~ 10
9
neutrons/s.
Detailed design of PNG and modeling of neutron for-
mation, inhibition and absorption processes are present-
ed in [8].
In this paper, we indicate only the main characteris-
tics of PNG (Fig. 1). The main idea is that the deuterons
dispersed in the electrostatic accelerators fall on the
target from beryllium, as a result of which neutrons of
energies of ~ 2…4 MeV are formed. It is important to
point out that the deuteron beam hits the target through
a narrow ion-conducting needle, which allows for some
cases of cancer to provide a sufficient therapeutic dose
of radiation by placing the source in close proximity to
the tumor. We note that the requirement of a narrow ion
conductor leads to limitations on the intensity of the
deuteron beam and, consequently, the yield of neutrons.
At the same time, the structure of the neutron field is
such that the dose absorbed by the healthy tissue is
small (Fig. 2). The absorbed dose of Fig. 2,b,c is calcu-
lated for cases of a point target and a target of finite size
placed in a water phantom.
The ion conductor is cooled by water, so the temper-
ature of the outer surface of the ion conductor (includ-
ing the neighborhood of the beryllium target) can be
controlled by changing the water temperature in the
cooling circuit. Consequently, it is easy to create com-
fortable conditions for the patient.
Numerical realization of the simulation of the neu-
tron field provides for the use of momentum and energy
conservation laws for each event, i.e. we can say that
the simulation is carried out "from the first principles".
Details of the modeling algorithms and the features
of the numerical implementation of the algorithm are
presented in [8].
POSSIBILITY OF PNG APPLICATION
IN ONCOLOGY
Fig. 2 above shows the distribution of the absorbed
dose of neutrons in the case of a point source of neu-
trons and a source of finite dimensions. It is important
that the absorbed dose is concentrated in a small neigh-
borhood (~ 2…3 cm.) from the neutron source of the
PNG target. At the same time, the absorbed dose de-
creases rapidly with the distance from the center of the
source, therefore, the natural distribution of the ab-
sorbed dose field is exactly what is necessary for effec-
tive therapy- it is mainly the diseased tissue of the or-
ganism that is irradiated. The very organism of the pa-
tient (and the tissue of the organism is, to a large extent,
water) acts as a retarder-reflector of neutrons. In this
case, there is a significant difference between the field
of neutrons produced in the reactor (irradiation with a
narrow neutron "ray" obtained with the help of collima-
tors) and irradiation of PNG. In both cases, a sufficient
absorbed dose can be obtained, but in the case of using
the reactor it is impossible (or at least very difficult) to
deliver the neutron source to the tumor in the body.
In practice, the source of neutrons is delivered di-
rectly to the tumor by injecting into the body of the pa-
tient an ion-conductor needle-brachytherapy takes place.
Brachytherapy in the general case involves the delivery
of a source of neutrons to the site of the tumor. The pe-
culiarities of the human body (and the presence of a
narrow ion-conductor-PNG needle) make it possible in
a number of cases (for example, in the treatment of uter-
ine cancer in women or prostate cancer in men) to de-
liver a neutron source to the tumor site without surgical
intervention.
Alternative use of PNG for tumor irradiation is to
place the source of neutrons outside the patient's body,
but close to the body surface (as should be done in the
treatment, for example, of melanoma).
Consider the problem of assessing the impact of
neutrons on personnel. At the same time, we place the
neutron generator in a bunker with thick concrete walls.
ISSN 1562-6016. ВАНТ. 2017. №6(112) 173
a
b
c
Fig. 1. a) General scheme of PNG; b) Absorbed dose
(Gy / min) as a function of the distance from a point
source of neutrons (cm); c) Dose distribution along
the Y axis at a finite ion source, Neutron source,
perpendicular to the Z-axis, of size ~ 11 cm
In fact, similar estimates can easily be made for any
set of rooms, but it should be noted that thin walls or
large openings in walls (doors, windows) may cause
harmful radiation exposure to personnel. Therefore, the
methodology for assessing the danger (or lack of dan-
ger) of the work of PNG for personnel should be con-
sidered as a model for similar calculations in relation to
the actual premises in which the facility will be located.
PNG is installed in a bunker with concrete walls of
thickness D = 1 m. The neutron yield is Wneutron ~ 10
9
N/s.
Neutrons and γ-radiation can penetrate through the con-
crete wall to the adjacent room L1L2L3 =
600800900 cm, dimensions of the bunker
L1bL2bL3b = 300300400 cm. We assume (within
the general principle of assessing the danger from
above) that neutrons remain fast, with all the neutrons
leaving the patient's body. The layout of the installation
in the bunker and the adjacent room is shown in Fig. 2
Fig. 2. Location of PNG installation in the bunker
and adjacent room
Let us estimate the value of the flux density of
gamma radiation at point A (see Fig. 2) behind the
wall separating the bunker from the adjacent room. Data
on the irradiation weakening in concrete, as subsequent-
ly data on the weakening of the neutron flux in concrete,
is taken from the handbook [9]:
9
100
33 2.410
4 300 300 2 300 400 2
1.157
MeV
e
cm s
(1)
it is easy to see that the radiation flux density is negligi-
ble (we achieved this by placing the stand in a hopper
with sufficiently thick walls).
Let us perform a similar estimate for the neutron
field (estimate for the neutron albedo, η = 0.8).
8
100
0 26 2.43 6 10
1 4 300 300 2 300 400N e
,
09
100
6 300 40026 2.46 10
1 4 300 300 2 300 400 1 2 600 800 600 900 800 900 2
20N
N
N
e
cm c
09
100
6 300 40026 2.46 10
1 4 300 300 2 300 400 1 2 600 800 600 900 800 900 2
20 .N
N
N
e
cm s
(2)
PNG Bunker
Accelerator envelope
Deutron source
Deutron bunch
«Needle»
Vacuum pump
Electrods
Vacuum tube
Gradient rings
Elegas
Water delivery
Dosa
cm
cm
ISSN 1562-6016. ВАНТ. 2017. №6(112) 174
The density of the neutron flux is close to the per-
missible flux density of fast neutrons for personnel in
Category A according to НРБ-99, which is acceptable.
CONCLUSIONS
The portable neutron generator developed at the
NSC KIPT can be used to treat certain oncological dis-
eases, without surgical intervention. Within a few
minutes of the generator's work, a sufficient dose of
neutron irradiation is absorbed by diseased tissues, at
the same time, due to the obtained structure of the neu-
tron field, the damage to healthy cells is minimal.
Estimates of the effect of radiation on the environ-
ment, in particular, evaluation of the characteristics of
the neutron field in the bunker, where the neutron gen-
erator is located, and the adjacent room are performed.
It is shown that there is no danger to the personnel in
this case. A similar calculation should be made each
time the installation location is selected.
REFERENCES
1. B. Bayanov et al. Accelerator based neutron source
for the neutron-capture and fast neutron therapy at
hospital // Nucl. Instr. and Meth. in Phys. Res. 1998,
A 413, p. 397.
2. V. Kononov, M. Bokhovko, O. Kononov. Accelera-
tor based neutron sources for medicine // Proceed-
ings of International Symposium on Boron Neutron
Capture Therapy / Ed., Sergey Yu. Taskaev, July 7-
9, 2004, Novosibirsk, Russia, p. 62-68.
3. А.В. Важенин, Г.Н. Рыкованов. Уральский центр
нейтронной терапии: история, методология, ре-
зультаты. M.: Издательство РАМН, 2008, 143 с.
4. T. Blue and J. Yanch. Accelerator-based epithermal
neutron sources for boron neutron capture therapy of
brain tumors // Journal of Neuro-oncology. 2003,
v. 62, p. 19-31.
5. Leon Forman and Keith T. Welsh // International
Conference on Portable Neutron Generators and
their Applications. Moscow, Russia, 2004, Oct. 18-
22, p. 153-168.
6. K.T. Welsh, L. Forman, L. Reinstein, A.J. Meek. Ion
Beam and Neutron Output Performance of a Portable
Accelerator Based Brachytherapy Neutron Source //
44st annual meeting of the American Association of
Physicist in Medicine, Salt Lake City, Ut 2002.
7. L. Forman. Small generator using a high current
electron bombardment ion source and methods of
treating tumor therewith // United States patent 6,
925, 137 B1, Aug. 2, 2005.
8. А.N. Dovbnya, V.А. Tsymbal, A.F. Stoyanov. Nu-
merical simulation of neutron flow exposure on the
organic tissues // Problems of Atomic Science and
Technology. Series “Nuclear Physics
Investigations”. 2015, № 6, p. 165-168.
9. V. Mashkovich, T. Kudryavceva. Radiational
shielding handbook. Moscow, 1996, 496 p.
Article received 17.10.2017
О ВОЗМОЖНОСТИ ИСПОЛЬЗОВАНИЯ ПОЛЯ ПОРТАТИВНОГО НЕЙТРОННОГО ГЕНЕРАТОРА
ДЛЯ ЛЕЧЕНИЯ ОНКОЛОГИЧЕСКИХ ЗАБОЛЕВАНИЙ
А.Ф. Стоянов, А.Н. Довбня, В.А. Цымбал
Рассматривается возможность применения портативного нейтронного генератора (ПНГ) для лечения он-
кологических заболеваний. Показано, что при применении ПНГ в качестве источника нейтронов можно
обеспечить достаточное терапевтическое воздействие на больные клетки, с минимальным повреждением
здоровых клеток. Речь идет о применении ПНГ при брахитерапии опухоли. Важно отметить, что наличие
узкого ионопровода «иглы» позволяет разместить источник нейтронов близко к опухоли, а следовательно,
усилить терапевтическое воздействие. Выполнены численные оценки плотности потока нейтронов и погло-
щенной дозы при использовании ПНГ для брахитерапии, показано, что в течение небольшого промежутка
времени (~1 минуты) поглощается достаточная для терапии доза излучения. Расчеты потока нейтронов и
поглощенной дозы выполнены с помощью разработанной авторами компьютерной программы, основанной
на применении метода Монте-Карло и предназначенной для моделирования процессов образования, движе-
ния, торможения и поглощения нейтронов.
ЩОДО МОЖЛИВОСТІ ЗАСТОСУВАННЯ ПОЛЯ ПОРТАТИВНОГО НЕЙТРОННОГО
ГЕНЕРАТОРА ДЛЯ ЛІКУВАННІ ОНКОЛОГІЧНИХ ЗАХВОРЮВАНЬ
О.Ф. Стоянов, А.М. Довбня, В.О. Цимбал
Розглядається можливість застосування портативного нейтронного генератора (ПНГ) для лікування он-
кологічних хвороб. Показано, що за умови застосування ПНГ в якості джерела нейтронів можна забезпечити
достатній терапевтичний вплив на хворі клітини, з мінімальним ураженням здорових клітин. Мова йде про
застосування ПНГ при брахітерапії пухлини. Важливо зауважити, що наявність вузького іонопровода «гол-
ки» дає можливість розташувати джерело нейтронів у безпосередній близькості до пухлини, а отже підси-
лити терапевтичну дію. Виконані чисельні оцінки щільності потоку нейтронів і поглиненої дози під час за-
стосування ПНГ у брахітерапії, показано, що протягом невеликого проміжку часу (~1 хвилини) поглинаєть-
ся достатня для терапії доза опромінювання. Обчислення потоку нейтронів і поглиненої дози виконано за
допомогою розробленої авторами комп’ютерної програми, заснованої на методі Монте-Карло і призначеної
для моделювання процесів створення, руху, гальмування та поглинання нейтронів.
|