EP1047083B1 - A neutron amplifier assembly - Google Patents
A neutron amplifier assembly Download PDFInfo
- Publication number
- EP1047083B1 EP1047083B1 EP99107327A EP99107327A EP1047083B1 EP 1047083 B1 EP1047083 B1 EP 1047083B1 EP 99107327 A EP99107327 A EP 99107327A EP 99107327 A EP99107327 A EP 99107327A EP 1047083 B1 EP1047083 B1 EP 1047083B1
- Authority
- EP
- European Patent Office
- Prior art keywords
- cylinder
- neutron
- layer
- fissile material
- assembly according
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Lifetime
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-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G4/00—Radioactive sources
- G21G4/02—Neutron sources
Definitions
- Figure 3 shows a variant which is conceived to produce a high flux of fast neutrons.
- Figure 4 is an improved embodiment with two subcritical arrays in series.
- the fissile material is Am 242m .
- This material constitutes a thin layer 1 on the inner surface of a hollow cylinder 2 of circular cross-section, made of a neutron moderator material such as graphite or beryllium.
- a spallation target 3 is located which is intended to receive a proton beam from an accelerator (not shown) along the axial direction of the cylinder 2.
- the cylinder height and its inner diameter are both 1 m, the diameter of the target 3 being 30 cm.
- Neutrons starting from the target 3 may be either thermal or fast neutrons.
- the cylinder 2 is not necessarily of circular cross-section as shown in the drawings.
- the cross-section might be square or present an inner corrugated shape like a star. In this latter case the overall diameter of the cylinder 2 can be reduced whilst maintaining the same surface area of fissile material.
- the heat production in the arrangement is rather low: Taking the above cited example of a 150 MeV accelerator supplying a proton current of 2 mA (corresponding to 300 kW power output) and a neutron amplification factor of 20 due to the layer 1 of fissile material, the neutron intensity will become about 2,5 ⁇ 10 17 s -1 . Since the neutron generation rate is approximately equal to the rate of fissioning, the maximum heat generation rate is about 8 MW. This heat can be easily extracted through coolant channels in the graphite cylinder.
- two or more layers of fissile material are located, preferably in a concentric axial configuration, between the spallation target and the inner diameter of the graphite cylinder.
- a concentric axial configuration between the spallation target and the inner diameter of the graphite cylinder.
- one additional layer 6 of fissile material is added which is either self-supporting or deposited on a metal tube, for example made of tungsten (not shown).
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- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- General Chemical & Material Sciences (AREA)
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Particle Accelerators (AREA)
- Measurement Of Radiation (AREA)
- Dental Preparations (AREA)
- Steroid Compounds (AREA)
- Semiconductor Lasers (AREA)
- Steering Control In Accordance With Driving Conditions (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Addition Polymer Or Copolymer, Post-Treatments, Or Chemical Modifications (AREA)
- Tires In General (AREA)
Abstract
Description
- This invention refers to a neutron amplifier assembly comprising a slightly subcritical array of fissile material which is subjected to a primary neutron flux.
- A neutron flux is used not only for research purposes but also for irradiating goods, for cancer treatment and even for controlling a nuclear power generator. For example, a high neutron intensity above 1017 s-1 would be useful for many purposes. Such a high flux is beyond the practical possibilities of modern accelerators, even in combination with a spallation target. It is therefore an object of the present invention to provide a neutron amplifier assembly which supplies an intense and readily controllable neutron flux.
- This object is achieved according to the invention by the neutron amplifier assembly as defined in
claim 1. For further improvements of this assembly reference is made to the secondary claims. - The invention will now be described in detail by means of some preferred embodiments and the enclosed drawings.
- Figure 1 shows schematically in cross-section a first embodiment of the assembly according to the invention.
- Figure 2 shows the relation between the mass and layer thickness of fissile material in the hollow cylindrical arrangement of given dimensions for keff = 1.
- Figure 3 shows a variant which is conceived to produce a high flux of fast neutrons.
- Figure 4 is an improved embodiment with two subcritical arrays in series.
- According to a first embodiment shown in figure 1, the fissile material is Am242m. This material constitutes a
thin layer 1 on the inner surface of ahollow cylinder 2 of circular cross-section, made of a neutron moderator material such as graphite or beryllium. Along the axis of this cylinder aspallation target 3 is located which is intended to receive a proton beam from an accelerator (not shown) along the axial direction of thecylinder 2. As an example, the cylinder height and its inner diameter are both 1 m, the diameter of thetarget 3 being 30 cm. - The thickness of the
layer 1 is in the micrometer range and will be specified later. This thickness depends upon the type of fissile material and its concentration in this layer. In any case it must be sufficiently small in order to allow fast neutrons to pass there-through without interaction, whereas thermal neutrons are trapped. - Neutrons starting from the
target 3 may be either thermal or fast neutrons. - Thermal neutrons react immediately with the
layer 1 and generate fast neutrons whereas fast neutrons pass there-through without interaction. In both cases fast neutrons penetrate into thegraphite cylinder 2 and become thermalized. If these neutrons penetrate again into thelayer 1 they cause more fissions. Those which escape from the cylinder at its outside constitute the output of the amplifier assembly. - It should be noted that the thickness of the fissile material layer on the inner surface of the graphite cylinder should be such that the arrangement does not become critical, but a criticality factor keff close to 1 should be achieved in order to enhance the neutron amplification gain.
- The tables following here-after show, for a cylinder having an inner diameter equal to its height, the thickness of a layer of Am242m and U235 respectively required for various inner cylinder diameters necessary to make the system critical.
Layer thickness of Am242m metal and corresponding mass required for criticality for various cylinder diameters . (cm) critical thickness (cm) critical mass (kg) 10 0.4 2.6 20 0.063 1.6 30 0.005 0.25 40 0.001 0.1 60 0.0004 0.08 Layer thickness of U235 metal and corresponding mass required for criticality for various cylinder diameters . (cm) critical thickness (cm) critical mass (kg) 10 2 14 20 0.8 20 40 0.15 14 60 0.023 5 100 0.007 4 - These values are also represented in the plot of Figure 2 as small circles and crosses respectively. One can for example deduce there-from that criticality is obtained with an Am242m layer thickness of 4 µm on the inner surface (diameter 60 cm) of a graphite cylinder (axial length 60 cm). The overall critical mass of fissile material is under these circumstances only 80 g which is considerably less than the (bare) critical mass of a solid spere of the same material (4.7 kg).
- Thus if a thickness below 4 µm is chosen then the arrangement will be subcritical. If for example the criticality factor keff is 0.95 then its neutron amplification factor will become 20.
- A commercial cyclotron supplying a proton beam of 150 MeV produces in a lead spallation target about 1 neutron per proton. Due to the layer of fissile material this neutron produces on average M neutrons where M ≈ 1/(1 - keff). For the case of keff= 0.95, M is approximately 20.
- The invention is not restricted to the embodiment described above. One could employ other fissile materials, such as U235 (see table 2 and figure 2). It should further be noted that the invention is also applicable to materials others than pure fissile materials, in which the fissile material is present in the layer at a substantially reduced amount.
- It is also possible to cover the
inner layer 1 of fissile material with a layer of moderator material in order to reduce damages in the fissile material layer due to high energy neutrons. - The neutron source can instead of a spallation target consist of a neutron emitter such as Californium.
- The
cylinder 2 is not necessarily of circular cross-section as shown in the drawings. In fact, the cross-section might be square or present an inner corrugated shape like a star. In this latter case the overall diameter of thecylinder 2 can be reduced whilst maintaining the same surface area of fissile material. - The heat production in the arrangement is rather low: Taking the above cited example of a 150 MeV accelerator supplying a proton current of 2 mA (corresponding to 300 kW power output) and a neutron amplification factor of 20 due to the
layer 1 of fissile material, the neutron intensity will become about 2,5·1017 s-1. Since the neutron generation rate is approximately equal to the rate of fissioning, the maximum heat generation rate is about 8 MW. This heat can be easily extracted through coolant channels in the graphite cylinder. - In case that not a thermal neutron flux but a fast neutron flux is desired, the arrangement according to figure 1 should be completed, as shown in figure 3, by a further layer 4 of fissile material on the outer surface of the
graphite cylinder 2 and optionally by ametal casing 5 around this layer, especially made of tungsten. This second layer 4 is again transparent to fast neutrons as it interacts only with neutrons which have been thermalized in the graphite cylinder. These neutrons cause fissions which result in fast neutrons. A part of these fast neutrons escapes through the casing whereas others return into the graphite cylinder and cause further fissions in one of the layers of fissile materials. - According to a further improvement of the present invention two or more layers of fissile material are located, preferably in a concentric axial configuration, between the spallation target and the inner diameter of the graphite cylinder. Such an example is sketched in figure 4. Here, one additional layer 6 of fissile material is added which is either self-supporting or deposited on a metal tube, for example made of tungsten (not shown).
- As a further improvement, one or more moderator rods (not shown) can be inserted in a controlled manner into the free space inside the graphite cylinder. This insertion increases the criticality factor and allows a fine control of the neutron amplification factor and of the criticality factor, in order to take into account inhomogeneities of the thin layers and their burn-up.
Claims (7)
- A neutron amplifier assembly comprising an array of fissile material which is subjected to a primary neutron flux, characterized by a thin layer (1) of fissile material on the inner surface of a hollow support cylinder (2) of moderator material, the fissile material layer thickness and the inner diameter of said cylinder being chosen such that the array is close to criticality.
- An assembly according to claim 1, characterized in that at least one further thin cylindrical layer (4) of fissile material is placed in said cylinder at a distance from the previous layer (1), its diameter and thickness being chosen such that the overall configuration constitutes again a nearly critical array.
- An assembly according to claim 1, characterized in that the primary neutron flux is generated by a neutron emitter situated in the centre of the assembly.
- An assembly according to claim 3, characterized in that the neutron emitter is constituted by a spallation target (3) intended to be bombarded by accelerated particles.
- An assembly according to any one of the preceding claims, characterized in that the hollow cylinder (2) is made from graphite.
- An assembly according to any one of the preceding claims, characterized in that the hollow cylinder (2) is surrounded by a layer (4) of fissile material.
- An assembly according to any one of the preceding claims, characterized in that at least one moderator material rod is movably inserted into the free space in the hollow cylinder (2).
Priority Applications (11)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DK99107327T DK1047083T3 (en) | 1999-04-20 | 1999-04-20 | neutron |
DE69909962T DE69909962T2 (en) | 1999-04-20 | 1999-04-20 | Neutronverstärkersanlage |
EP99107327A EP1047083B1 (en) | 1999-04-20 | 1999-04-20 | A neutron amplifier assembly |
PT99107327T PT1047083E (en) | 1999-04-20 | 1999-04-20 | NEUTRAL AMPLIFIER STRUCTURE |
ES99107327T ES2204023T3 (en) | 1999-04-20 | 1999-04-20 | NEUTRON AMPLIFIER ASSEMBLY. |
AT99107327T ATE246394T1 (en) | 1999-04-20 | 1999-04-20 | NEUTRON AMPLIFIER SYSTEM |
PCT/EP2000/003179 WO2000063921A1 (en) | 1999-04-20 | 2000-04-10 | A neutron amplifier assembly |
JP2000612962A JP2002542496A (en) | 1999-04-20 | 2000-04-10 | Neutron amplifier assembly |
CA002368547A CA2368547A1 (en) | 1999-04-20 | 2000-04-10 | A neutron amplifier assembly |
NO20014840A NO20014840D0 (en) | 1999-04-20 | 2001-10-04 | Nöytronforsterkerenhet |
US10/698,459 US20040228433A1 (en) | 1999-04-20 | 2003-11-03 | Neutron amplifier assembly |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
EP99107327A EP1047083B1 (en) | 1999-04-20 | 1999-04-20 | A neutron amplifier assembly |
Publications (2)
Publication Number | Publication Date |
---|---|
EP1047083A1 EP1047083A1 (en) | 2000-10-25 |
EP1047083B1 true EP1047083B1 (en) | 2003-07-30 |
Family
ID=8237956
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP99107327A Expired - Lifetime EP1047083B1 (en) | 1999-04-20 | 1999-04-20 | A neutron amplifier assembly |
Country Status (10)
Country | Link |
---|---|
EP (1) | EP1047083B1 (en) |
JP (1) | JP2002542496A (en) |
AT (1) | ATE246394T1 (en) |
CA (1) | CA2368547A1 (en) |
DE (1) | DE69909962T2 (en) |
DK (1) | DK1047083T3 (en) |
ES (1) | ES2204023T3 (en) |
NO (1) | NO20014840D0 (en) |
PT (1) | PT1047083E (en) |
WO (1) | WO2000063921A1 (en) |
Families Citing this family (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP7074615B2 (en) * | 2018-08-27 | 2022-05-24 | 株式会社東芝 | Neutron supply device and neutron supply method |
GB2625606A (en) * | 2022-11-02 | 2024-06-26 | Aurelia Lumina Ltd | Power source |
Family Cites Families (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
BE567050A (en) * | 1957-04-24 | |||
US3778627A (en) * | 1973-04-17 | 1973-12-11 | Atomic Energy Commission | High intensity, pulsed thermal neutron source |
SU786619A1 (en) * | 1979-07-16 | 1991-08-15 | Предприятие П/Я Г-4665 | Two-stage multiplier of neutrons |
BE1008113A3 (en) * | 1994-03-04 | 1996-01-23 | Ion Beam Applic Sa | Method for producing thermal neutron device for implementing the method and use for production radioisotope. |
-
1999
- 1999-04-20 PT PT99107327T patent/PT1047083E/en unknown
- 1999-04-20 EP EP99107327A patent/EP1047083B1/en not_active Expired - Lifetime
- 1999-04-20 DK DK99107327T patent/DK1047083T3/en active
- 1999-04-20 AT AT99107327T patent/ATE246394T1/en not_active IP Right Cessation
- 1999-04-20 DE DE69909962T patent/DE69909962T2/en not_active Expired - Fee Related
- 1999-04-20 ES ES99107327T patent/ES2204023T3/en not_active Expired - Lifetime
-
2000
- 2000-04-10 JP JP2000612962A patent/JP2002542496A/en not_active Withdrawn
- 2000-04-10 CA CA002368547A patent/CA2368547A1/en not_active Abandoned
- 2000-04-10 WO PCT/EP2000/003179 patent/WO2000063921A1/en active Application Filing
-
2001
- 2001-10-04 NO NO20014840A patent/NO20014840D0/en not_active Application Discontinuation
Also Published As
Publication number | Publication date |
---|---|
ATE246394T1 (en) | 2003-08-15 |
NO20014840L (en) | 2001-10-04 |
NO20014840D0 (en) | 2001-10-04 |
PT1047083E (en) | 2003-12-31 |
WO2000063921A1 (en) | 2000-10-26 |
DK1047083T3 (en) | 2003-11-24 |
JP2002542496A (en) | 2002-12-10 |
DE69909962D1 (en) | 2003-09-04 |
ES2204023T3 (en) | 2004-04-16 |
DE69909962T2 (en) | 2004-05-27 |
CA2368547A1 (en) | 2000-10-26 |
EP1047083A1 (en) | 2000-10-25 |
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