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Neutron Detection Systems for Nuclear Reactors
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A detection system and a technology for a neutron detection device are applied in the field of reactor systems and can solve the problems of inability to verify neutron activity, inability to detect or confirm the existence of neutron sources, etc.
Active Publication Date: 2018-10-02
NUSCALE LLC
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[0010] A neutron source that does not have and / or loses the ability to generate a sufficient number of neutrons in one or more modes of reactor operation would result in the inability of reactor monitoring instrumentation to detect or confirm the presence of the neutron source and / or the inability to verify the associated neutron active
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[0027] Various examples disclosed and / or referred to herein may operate in concert or in conjunction with one or more features found in U.S. Application No. 11 / 941,024 and / or U.S. Application No. 12 / 397,481, which The entire content of is hereby incorporated by reference.
[0028] figure 1 An example nuclear reactor module 5 is shown comprising a reactor core 6 surrounded by a reactor pressure vessel 2 . The coolant 10 in the reactor pressure vessel 2 surrounds the reactor core 6 . The reactor core 6 may be located in a shroud 22 that surrounds the reactor core 6 around its sides. As the coolant 10 is heated through the reactor core 6 due to a fission event, the coolant 10 may be directed from the shroud 22 upwards into the annulus 23 above the reactor core 6 out of the riser 24 . This causes additional coolant 10 to be drawn into the shroud 22 to be subsequently heated by the reactor core 6 which draws more coolant 10 into the shroud 22 . The coolant 10 emerging from the ...
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Abstract
The neutron detection system (300, 400, 500, 600, 700, 800) may include a neutron detection device (325, 425, 525, 625, 725, 825) located outside the reactor vessel (2). The neutron detection device may be configured to detect neutrons generated within the reactor vessel. A secure region (14, 414, 514, 614, 714, 814) intermediate the reactor vessel and containment vessel may be configured to contain a secure medium. A neutron path arrangement (475, 575, 675, 775, 875) may be located at least partially between the reactor vessel and the containment vessel, and the neutron path arrangement may be configured to pass a neutron path medium ( 430, 530, 630, 730, 830) provide a neutron path (440, 540, 640, 740, 840) to a neutron detection device. The neutron attenuation coefficient associated with the neutron path medium may be less than the neutron attenuation coefficient associated with the safety medium.
Description
[0001] Cross References to Related Applications [0002] This application claims priority to U.S. Provisional Application No. 61 / 921,037, filed December 26, 2013, and U.S. Non-Provisional Application No. 14 / 242,677, filed April 1, 2014. technical field [0003] The present application relates to the field of power generation, which relates to reactor systems operating using neutron sources and / or neutron detectors. Background technique [0004] Fission-type nuclear reactors may be configured to slow or moderate the neutrons produced by nuclear fission using neutron moderators in order to increase the cross-section of the fuel source. The increased cross-section can in turn increase the number of neutrons that can cause a fission event rather than being captured by the fuel source, and thereby propagate the chain reaction of the ensuing fission event. [0005] Thermal neutrons are free neutrons, which may have a kinetic energy of about 0.025 eV and / or a velocity of 2.2 km / s ...
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