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CONTENTS
목차
제1장 연구개발과제의 개요 21
제2장 국내외 기술개발 현황 33
제3장 연구개발 수행 내용 및 결과 37
제1절 빔-표적 중성자 발생장치 37
제2절 원통형 중성자 발생장치 63
제3절 중성자 차폐 및 인허가 79
제4절 He-3 검출기를 이용한 중성자 발생률 측정방법 확립 90
제4장 연구개발 목표 달성도 및 관련 분야 기여도 96
제5장 연구개발결과의 활용계획 102
제6장 참고문헌 103
Table 1-1-1. Various neutron sources. 22
Table 1-1-2. Specification of various neutron generators. 24
Table 3-1-1. Material property table for electrode candidate matters. 40
Table 3-1-2. Input parameters of CFX 5.7 code calculation. 54
Table 3-1-3. Results of CFX 5.7 code running and neutron yield. 54
Table 3-1-4. Various conditions of neutron generation runs. 60
Table 3-3-1. Dose equivalent rate at various position without borated P.E. (a ~ h are noted in Fig. 3-3-5) 85
Table 3-3-2. Dose equivalent rate at various position with borated P.E. (a ~ h are noted in Fig. 3-3-5) 85
Table 3-3-3. Measured dose equivalent rate at various positions noted on Fig. 3-3-7. 87
Fig. 1-1-1. Cross section of D-D and D-T reactions. 23
Fig. 1-1-2. Neutron generation device LANCELOT. 26
Fig. 1-1-3. SODITRON, commercial neutron generation tube sold by EADS sodern. 26
Fig. 1-1-4. Schematic drawing of the spherical IEC device at Illinois university. 26
Fig. 1-1-5. Schematic drawing of the LBNL neutron source. 27
Fig. 3-1-1. Schematic drawing of the helicon ion source with triple electrode system. 38
Fig. 3-1-2. Ion beam trajectory calculated by using IGUN code. 41
Fig. 3-1-3. Measured ion beam current and related parameters.(자장전류:전자식 전원 전류, 인출 전압:이온원 전원 전압, 인출 전류:이온원 전원 전류, 빔전류:이온빔 인출 전류) 41
Fig. 3-1-4/3-1-9. Picture of the slit for ion beam screening. 42
Fig. 3-1-5/3-1-10. Picture of the Faraday cup. 42
Fig. 3-1-6/3-1-11. Current of ion beam passed through the slit. (Case 1:740 W, case 2:800 W, case 3:900 W) 43
Fig. 3-1-7. Radial distribution of ion beam current vs. RF power and extraction voltage. 44
Fig. 3-1-8. Schematic drawing of the beam-target neutron generator. (Prototype ion source is used) 45
Fig. 3-1-9. Drawing of the new titanium target and target assembly. Cap (a), new titanium target (b), body (c) and the assembled (d). 46
Fig. 3-1-10. Block diagram of the detection system 46
Fig. 3-1-11. Si detector energy spectrum. (Proton peak:1.80 MeV, FWHM:155 keV) 47
Fig. 3-1-12. He-3 detector signal spectrum 48
Fig. 3-1-13. Neutron yield vs. deuteron beam energy and time. (Target:40 μm thick). 48
Fig. 3-1-14. Neutron yield response to deuteron beam energy along time. (Target:1 ㎜ thick) 49
Fig. 3-1-15. Neutron yield vs. deuteron beam energy at various target thickness. 50
Fig. 3-1-16. D/Ti ratios of various targets at various beam current and beam energy. 51
Fig. 3-1-17. Auger electron spectra of the titanium drive-in target measured at surface and deep layer. (Target:40 μm thick). 52
Fig. 3-1-18. Result of sputtering depth profiling with AES of the titanium target. Out of deuteron beam irradiation area (a), at the center of irradiation area (b). 52
Fig. 3-1-19. Variation of neutron yield by change of cooling condition. Neutron yield is normalized to 1.54×107 n/s.(이미지참조) 53
Fig. 3-1-20. Beam current distribution according to σ of 2-D cylindrically symmetric Gaussian function. 55
Fig. 3-1-21. Temperature distribution on the front surface of Ti target. 56
Fig. 3-1-22. Maximum temperature at the target surface vs. deposited beam power. (Coolant flow rate:10 lpm). 57
Fig. 3-1-23. Maximum temperature at the target surface vs. deposited beam power. (Coolant flow rate:25 lpm). 57
Fig. 3-1-24. Drawing of the neutron generator in plane view (a) and side view (b). 59
Fig. 3-1-25. Neutron yields vs. deuteron beam energy at every neutron generation run. 61
Fig. 3-1-26. D/Ti ratios plotted according to deuteron beam power at every neutron generation run. 61
Fig. 3-1-27. Neutron yield vs. deuteron beam energy and time. (Neutron generation run:I) 62
Fig. 3-2-1. Conceptual design of the cylindrical neutron generator. 63
Fig. 3-2-2. Schematic drawing of the cylindrical neutron generator with quadruple electrodes. 64
Fig. 3-2-3. Trajectory of ion beam accelerated to the center of the device. 65
Fig. 3-2-4. Capacitive probe (left), equivalent circuit of the diagnostic system (right). 66
Fig. 3-2-5. Calibration of the capacitive probe. 66
Fig. 3-2-6. Plasma RF potential measured using capacitive probe at various H₂ gas pressure 67
Fig. 3-2-7. Plasma RF potential vs. RF power (left), gas pressure (right). 67
Fig. 3-2-8. Plasma density (left), and plasma temperature (right) measured using Langmuir probe. 68
Fig. 3-2-9. Block diagram of heterodyne interferometry system (left), path of the diagnostic micro wave (right). 68
Fig. 3-2-10. Plasma density measured using Langmuir probe and microwave interferometry. (left:argon, right:hydrogen) 69
Fig. 3-2-11. Extracted ion beam current form hydrogen plasma. 70
Fig. 3-2-12. Cross sections of various collisions (left:H₂+, right: H+).(이미지참조) 71
Fig. 3-2-13. Pressure at plasma generation region and ion beam acceleration region according to the flow rate of hydrogen gas. 72
Fig. 3-2-14. Total conductance in the cylindrical neutron generator vs. slit length. 74
Fig. 3-2-15. Relation between P₃ and P₂ 75
Fig. 3-2-16. Required total conductance to satisfy the differential pumping condition of P₁/P₂ at various pimping speed. 76
Fig. 3-2-17. Schematic drawing of the modified cylindrical neutron generator with triple electrodes. 77
Fig. 3-2-18. Extracted ion beam current vs. slit length and RF power (a), beam mark left on Ti target (b). 77
Fig. 3-3-1. Arrangement of the radiation shields in plane view (a), and side view (b). (Unit in cm) 80
Fig. 3-3-2/3-3-52. Picture or the neutron shield room. P.E. structure of the neutron shield room (a), and the completed neutron shield room (b). 81
Fig. 3-3-3. Positions of the H-beams installed under the floor of the neutron generation lab. 82
Fig. 3-3-4. Picture of a H-beam installed to reinforce the floor of the neutron generation lab. 82
Fig. 3-3-5. Schematic view of geometrical condition for the calculation of radiation dose by using MCNP 4C2 code. 83
Fig. 3-3-6. Atomic percent of P.E (a) and borated P.E (b). 84
Fig. 3-3-7. Map for survey of neutron and gamma-ray dose rate. 86
Fig. 3-4-1. Schematic drawing of the He-3 neutron detector. 91
Fig. 3-4-2. Signal spectrum of He-3 detector by Cf-252 spontaneous fission neutron. 91
Fig. 3-4-3. Neutron counts vs. source-to-detector distance 92
Fig. 3-4-4. Variation of neutron flux averaged over the detector cell along source-to-detector distance with and without surrounding materials. 93
Fig. 3-4-5. The ratio of neutron flux at the detector cell calculated with air or concrete walls to that without surrounding materials. 93
Fig. 3-4-6. Neutron count efficiency of He-3 detector measured by using the beam-target neutron generator at source-to-detector distance of 330 mm. 94
Fig. 3-4-7. Neutron count efficiency of He-3 detector measured by using the beam-target neutron generator at source-to-detector distance of 880 mm. 95
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