Project of a fast neutron target based on a 10 MeV 300 kW proton accelerator

Project of targets for high intense neutron source is proposed. The source is based on a proton continuous accelerator with the 10 MeV particle energy and up to 300 kW mean beam power. Problems of fabrication of these targets are discussed. Hot solid state and liquid target designs are considered. M...

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Datum:2001
Hauptverfasser: Avilov, M.S., Gubin, K.V., Kot, N.Kh., Logatchev, P.V., Martyshkin, P.V., Morozov, S.N., Shiyankov, S.V., Starostenko, A.A., Andrighetto, A., Bao, Y.W., Tecchio, L., Kandiev, Ya.Z., Plokhoi, V.V., Samarin, S.I.
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Sprache:English
Veröffentlicht: Національний науковий центр «Харківський фізико-технічний інститут» НАН України 2001
Schriftenreihe:Вопросы атомной науки и техники
Online Zugang:http://dspace.nbuv.gov.ua/handle/123456789/79221
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Zitieren:Project of a fast neutron target based on a 10 MeV 300 kW proton accelerator / M.S. Avilov, K.V. Gubin, N.Kh. Kot, P.V. Logatchev, P.V. Martyshkin, S.N. Morozov, S.V. Shiyankov, A.A. Starostenko, A. Andrighetto, Y.W. Bao, L. Tecchio, Ya.Z. Kandiev, V.V. Plokhoi, S.I. Samarin // Вопросы атомной науки и техники. — 2001. — № 3. — С. 24-26. — англ.

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spelling irk-123456789-792212015-03-31T03:01:37Z Project of a fast neutron target based on a 10 MeV 300 kW proton accelerator Avilov, M.S. Gubin, K.V. Kot, N.Kh. Logatchev, P.V. Martyshkin, P.V. Morozov, S.N. Shiyankov, S.V. Starostenko, A.A. Andrighetto, A. Bao, Y.W. Tecchio, L. Kandiev, Ya.Z. Plokhoi, V.V. Samarin, S.I. Project of targets for high intense neutron source is proposed. The source is based on a proton continuous accelerator with the 10 MeV particle energy and up to 300 kW mean beam power. Problems of fabrication of these targets are discussed. Hot solid state and liquid target designs are considered. Maximum admissible target parameters are presented. Advantages and disadvantages of various types of target for neutron production are discussed. 2001 Article Project of a fast neutron target based on a 10 MeV 300 kW proton accelerator / M.S. Avilov, K.V. Gubin, N.Kh. Kot, P.V. Logatchev, P.V. Martyshkin, S.N. Morozov, S.V. Shiyankov, A.A. Starostenko, A. Andrighetto, Y.W. Bao, L. Tecchio, Ya.Z. Kandiev, V.V. Plokhoi, S.I. Samarin // Вопросы атомной науки и техники. — 2001. — № 3. — С. 24-26. — англ. 1562-6016 PACS numbers: 29.17.+w http://dspace.nbuv.gov.ua/handle/123456789/79221 en Вопросы атомной науки и техники Національний науковий центр «Харківський фізико-технічний інститут» НАН України
institution Digital Library of Periodicals of National Academy of Sciences of Ukraine
collection DSpace DC
language English
description Project of targets for high intense neutron source is proposed. The source is based on a proton continuous accelerator with the 10 MeV particle energy and up to 300 kW mean beam power. Problems of fabrication of these targets are discussed. Hot solid state and liquid target designs are considered. Maximum admissible target parameters are presented. Advantages and disadvantages of various types of target for neutron production are discussed.
format Article
author Avilov, M.S.
Gubin, K.V.
Kot, N.Kh.
Logatchev, P.V.
Martyshkin, P.V.
Morozov, S.N.
Shiyankov, S.V.
Starostenko, A.A.
Andrighetto, A.
Bao, Y.W.
Tecchio, L.
Kandiev, Ya.Z.
Plokhoi, V.V.
Samarin, S.I.
spellingShingle Avilov, M.S.
Gubin, K.V.
Kot, N.Kh.
Logatchev, P.V.
Martyshkin, P.V.
Morozov, S.N.
Shiyankov, S.V.
Starostenko, A.A.
Andrighetto, A.
Bao, Y.W.
Tecchio, L.
Kandiev, Ya.Z.
Plokhoi, V.V.
Samarin, S.I.
Project of a fast neutron target based on a 10 MeV 300 kW proton accelerator
Вопросы атомной науки и техники
author_facet Avilov, M.S.
Gubin, K.V.
Kot, N.Kh.
Logatchev, P.V.
Martyshkin, P.V.
Morozov, S.N.
Shiyankov, S.V.
Starostenko, A.A.
Andrighetto, A.
Bao, Y.W.
Tecchio, L.
Kandiev, Ya.Z.
Plokhoi, V.V.
Samarin, S.I.
author_sort Avilov, M.S.
title Project of a fast neutron target based on a 10 MeV 300 kW proton accelerator
title_short Project of a fast neutron target based on a 10 MeV 300 kW proton accelerator
title_full Project of a fast neutron target based on a 10 MeV 300 kW proton accelerator
title_fullStr Project of a fast neutron target based on a 10 MeV 300 kW proton accelerator
title_full_unstemmed Project of a fast neutron target based on a 10 MeV 300 kW proton accelerator
title_sort project of a fast neutron target based on a 10 mev 300 kw proton accelerator
publisher Національний науковий центр «Харківський фізико-технічний інститут» НАН України
publishDate 2001
url http://dspace.nbuv.gov.ua/handle/123456789/79221
citation_txt Project of a fast neutron target based on a 10 MeV 300 kW proton accelerator / M.S. Avilov, K.V. Gubin, N.Kh. Kot, P.V. Logatchev, P.V. Martyshkin, S.N. Morozov, S.V. Shiyankov, A.A. Starostenko, A. Andrighetto, Y.W. Bao, L. Tecchio, Ya.Z. Kandiev, V.V. Plokhoi, S.I. Samarin // Вопросы атомной науки и техники. — 2001. — № 3. — С. 24-26. — англ.
series Вопросы атомной науки и техники
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fulltext PROJECT OF A FAST NEUTRON TARGET BASED ON A 10 MEV 300 KW PROTON ACCELERATOR M.S. Avilov, K.V. Gubin, N.Kh. Kot, P.V. Logatchev, P.V. Martyshkin, S.N. Morozov, S.V. Shiyankov, A.A. Starostenko, A. Andrighetto1, Y.W. Bao1, L. Tecchio1, Ya.Z. Kandiev2, V.V. Plokhoi2, S.I. Samarin2 Budker Institute of Nuclear Physics, 11, Ac. Lavrentiev Ave, Novosibirsk, 630090, Russia 1Laboratori Nazionali di Legnaro, Istituto Nazionale di Fisica Nucleare (LNL-INFN), Via Romea 4 - 35020 Legnaro (Padova) Italy 2Russian Federal Nuclear Center Russian Research Institute of Technical Physics, 13 Vasiliev St, Snezhinsk, 456770, Russia Project of targets for high intense neutron source is proposed. The source is based on a proton continuous accelera- tor with the 10 MeV particle energy and up to 300 kW mean beam power. Problems of fabrication of these targets are discussed. Hot solid state and liquid target designs are considered. Maximum admissible target parameters are presented. Advantages and disadvantages of various types of target for neutron production are discussed. PACS numbers: 29.17.+w 1 INTRODUCTION The low-energy proton beam of small transverse size (∼ 1 cm) and high mean beam power causes a high den- sity of energy deposition in a small volume of the target. The typical stopping length for protons of 10 MeV ener- gy occurs to be less than 1 mm for some materials. The main problem for target irradiated with the high-power beam is a heat removal from the active tar- get area. This problem may be solved by the target sur- face extension for solid targets, or by use of liquid metal as a target operational substance. If the proton beam size can be increased in diameter up to 10 cm or more, it seems reasonable to use the stationary solid state target for neutron production. Otherwise, the rotated or liquid metal targets should be used. Another serious problem is to choose the proper tar- get material. The following materials have high neutron production ratio: 13C, boron compounds, lithium, beryl- lium. 2 STATIONARY BERYLLIUM TARGET When the proton beam size is rather large, the sta- tionary beryllium target can be used for high neutron flux production. The layout of this target is presented in Fig. 1. To avoid a target surface overheating, it is reason- able to produce the target of a conical shape that effec- tively extends its active area. This target is cooled by liquid agent, for example, water or liquid metal. In the latter case the size of the target should be essentially re- duced. Parameters of the target cooled both by water and sodium - potassium alloy are presented in Table 1. The beam has a gaussian shape with σr=3.5 cm. Fig. 1. Layout of the conical target with liquid agent cooling. 1 – operational layer, 2 – intermediate lay- er of liquid metal, 3 – conical backing with cooling channels, 4 – vacuum chamber, 5 – inlets and out- lets of cooling channels, 6 – neutron beam output window, 7 – primary beam, 8 - collimator. The intermediate layer of sodium-potassium alloy is used in order to decrease the thermo-mechanical stress in target elements. Maximum stress for the target cooled by water is 10.8∙107 Pa, and maximum temperature of beryllium should be 2000C. Table 1. Parameters of the fixed beryllium target Water Na – K alloy Target length, m 0.9 0.4 Max. cone radius, m 0.06 0.06 Number of cooling channels 89 39 Coolant consumption, lpm 339 292 Max. coolant velocity, m/s 22 27 For the target cooled by the Na – K alloy the maxi- mum stress is 25∙107 Pa and maximum temperature of beryllium is 350ºC. 3 ROTATING TARGET ВОПРОСЫ АТОМНОЙ НАУКИ И ТЕХНИКИ. 2001. №3. Серия: Ядерно-физические исследования (38), с. 24-26. 24 A serious drawback of the target presented above is its large size and, as a result, a low density of neutron flux. When the beam size is rather small, the rotating 13C or boron compound based target seems to be the most attractive. These materials stand well the high tem- perature, and coolant is not required, since target cool- ing is carried out by thermal radiation. The target layout is shown in Fig. 2. The target rep- resents the rotating titanium disk with the diameter ap- proximately 1-1.5 m. The disk rim is assembled from graphite or B4C plates. Plate thickness is about 2 mm (stopping length of 10 MeV protons in graphite and boron carbide is about 0.7 mm), width – 1-2 cm, length – 10-12 cm. The disk is set on the shaft 5 cm in diame- ter. Fig. 2. Layout of rotating target. Target rotation is carried out with a frequency of 30-50 Hz and transferred to the vacuum chamber via a magnetic clutch. The dissipation of heat is carried out in two water-cooled semi-circle aluminum channels. Chan- nels have two gaps: operating one for incident beam, and technical one for temperature measurements (bolometer). A graphite collimator, which also acts as a beam position monitor, is placed opposite to the target. Behind the target the special graphite plate is placed for chamber protection and converter damage indication. The whole device is positioned inside the radiation shielding. Fig. 3. Temperature distribution over the carbon plate irradiated by gaussian proton beam with σ =1 cm. Result of simulation of temperature distribution over the MPG-class graphite plate irradiated by 300 kW gaussian proton beam is shown in Fig.3. The target di- ameter is 1 m. The front surface of the target is hotter than the rear one, and the highest temperature is ob- served near the point with maximum power deposition. Highest temperature does not exceed 20500C. The maxi- mum termo-mechanical stress is about 107 Pa, that is 2 – 4 times less than the ultimate stress for graphite. Another material suitable for intense neutron flux production is boron carbide. The production ratio for this material is higher than for carbon. Otherwise, the thermal conductivity of boron carbide is less than the one of carbon. As a result the temperature of the target hot area is 30% higher than for carbon target. Fig. 4. Highest temperature of boron carbide and carbon targets for various beam sizes vs. cyclic mo- tion amplitude. The maximum temperature of boron carbide and car- bon targets for various beam size is shown in Fig. 4. Points correspond to the maximum temperature of car- bon target at a beam size of 0.5 cm, 1 cm, 1.25 cm (top to bottom). The most reliable temperature of the target seems to be 2000O – 2100OC. To decrease the tempera- ture to this value, the effective target area has to be ex- tended by the cyclic motion of the target axis in vertical direction. The acceptable temperature value is reached when the motion amplitude is 2.5 – 3 cm. The maximum thermomechanical stress of boron carbide target is about 108 Pa that is 500 times less than its ultimate stress. 4 LIQUID METAL TARGET The target where the hot area is removed from the active zone is based on the liquid lithium technology and usually represents a liquid lithium jet. Such a target requires large consumption of liquid lithium. In this pa- per the alternative type of target is proposed. Liquid lithium is contained in a special tank - liquid lithium container (LLC), its sketch is shown in Fig 5. To avoid the local overheating, the liquid lithium has to be mixed up intensively. As a result, high-tempera- ture liquid lithium layers are mixed up with low-temper- ature layers. The typical mixing size is approximately a few spot sizes of proton beam. By this way, the liquid lithium mean temperature is maintained fixed except the area, located directly under the proton beam. ВОПРОСЫ АТОМНОЙ НАУКИ И ТЕХНИКИ. 2001. №3. Серия: Ядерно-физические исследования (38), с. 25-26. 25 Fig. 5. Sketch of liquid lithium container. 1– inci- dent proton beam, 2– cooling channels, 3 – liquid lithium, 4 – mixed-up device, 5 – container wall, 6 - preliminary heating device. High melting point of lithium (190OC) disables the use of water as a cooling agent, so liquid metals should be used as a heat carrier. After lithium is melted inside the tank, liquid metal should be loaded inside the cool- ing contour. Liquid metal coolant selection is defined by its melt- ing point. Melting temperature has to be as low as possi- ble, not higher than 30 – 40OC. Low melting tempera- ture allows to decrease the mean operation temperature of liquid lithium, because the efficiency of LLC de- pends directly on the temperature difference between container wall and heat carrier. So, the higher the tem- perature difference is, the stronger the heat transfer should be. The mean lithium temperature should not ex- ceed 300–350OC, otherwise its strong evaporation takes place. Since lithium is rather active chemical element, the corrosion resistance of material in liquid lithium envi- ronment strongly depends on admixtures content in it. Low carbon stainless steel stands well in liquid lithium environment and has rather high thermal conductivity (90 W/m∙K against, for example, titanium, whose ther- mal conductivity does not exceed 20 W/m∙K). Only a few metals with a low melting temperature can be used as liquid metal heat carriers. Examples are sodium or potassium. These metals, however, have melting points around 100 OC. Sodium-potassium alloy, which is applied in nuclear reactors, has lower than pure sodium or potassium melting temperature - down to -12.50C. So, this material has been suggested to use as a liquid metal heat carrier. Table 2. Main results of lithium container heat estima- tion Cooling channel diameter Heat carrier speed Maximum pressure differential in the channel Total heat-carrier consumption 1 cm 2.3 m/s 0.03 at 2.2 lps Lithium mean temperature Container internal surface temperature Cooling channel wall temperature Heat carrier initial temperature 230OC 213OC 184OC 30OC The estimation of thermomechanical stress shows that the overheat of the container wall should not exceed 120OC for steel as a wall material. Main results of LLC heat estimation are presented in Table 2. 5 CONCLUSION The advantages and disadvantages for each type of neutron production target are summarized in Table 3. Some of these items require additional study. Various neutron target types may be used for various applications, for example, BNCT, radioactive ion beam production, material science application. Table 3. Comparison of various target types. Advantages Disadvantages Stationary beryllium target • absence of mechani- cal motion; • in the case of water cooling - no expen- sive materials; • ability to use a num- ber of materials for neutron production. • large source size; cooling channels are positioned so close to working area; • cooling agent is under the beam; • technology of working material deposition on the backing needs careful study. Rotating carbon target • radiation as an inter- mediate heat carrier; • reliability and sim- plicity of design; • target destruction does not lead to dis- astrous effects for the accelerator; • material annealing at high temperatures eliminates radiation defects and reduces mechanical stress; • high rate of by-prod- ucts diffusion from graphite at high tem- peratures; • the use of two rotat- ing targets allows to reduce the thermal stress at small trans- verse beam size, and the length of carbon plates at large beam size. • limited lifetime due to carbon evaporation; • high cost of mate- rial (13С); • if use glassy car- bon – complexity of plate treatment; • power extraction limit 200 W/cm2, thus the maximum proton beam power should not exceed 300 kW; • target thickness grows with the beam energy raise. Liquid Lithium Container • ability to receive the high power beam; • no beam energy lim- it; • low velocity of liq- uid metal heat carri- er. • Intense evapora- tion at temperature higher than 400 − 450 OC; • Careful control of lithium tempera- ture is required; • Vertical or inclined proton beam. 26