An accelerator-based 99 mo subcritical production device and method
An accelerator-driven, production-device technology, applied in radiation-transforming chemical element devices, reactor/accelerator external conversion, nuclear engineering, etc., can solve problems such as high cost and complicated process, and achieve reduction of radioactive waste, simple post-processing, increased The effect of large reaction chances
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Embodiment 1
[0036] see Figure 1-2 : An accelerator-driven 99 Mo subcritical production device, including accelerator unit: S1, irradiation production unit S2 and separation and purification unit S3;
[0037] The accelerator unit S1 includes a high-energy particle source 10, a collimator 11, an accelerator 12, a target 13, and a target cavity 14 sequentially from the output direction. The target 13 in the central target cavity 14 of S2 produces neutron emission;
[0038] The irradiation production unit S2 is a concentric cylindrical structure, which sequentially includes a neutron moderator layer 20, a neutron multiplication layer 21, a low-enrichment uranium salt solution 22, a neutron reflection layer 23, and a shielding layer 24 from the inside to the outside; , the low-enrichment uranium salt solution 22 is placed in the fission reaction vessel 25 and sealed, and the emitted neutrons generated by the target 13 in the target cavity 14 pass through the neutron moderator layer 20 and t...
Embodiment 2
[0048] Embodiment 2 also discloses an accelerator-driven 99 Mo subcritical production method, comprises the following steps:
[0049] First, the accelerator unit generates accelerated particle beams (proton beams or deuterium ion beams) to bombard heavy nuclear targets (lead, mercury, tungsten), or gaseous deuterium targets (or tritium targets) in the target chamber, heavy nuclear fission occurs, or deuterium The deuterium fusion (or deuterium-tritium fusion) reaction emits neutrons;
[0050] The high-energy neutrons generated above enter the neutron moderator layer around the target chamber, and part of them are moderated to the thermal neutron area. 235 U has a larger fission cross section; wherein, the moderator layer material used is polyethylene, or water, or heavy water, or graphite, or beryllium, or zirconium hydride;
[0051] The neutron beam passing through the moderator layer enters the neutron multiplication layer I, and the material of this layer is bismuth, or l...
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