한국원자력연구원은 IAEA에서 권고하고 있는 안전조치기반설계(SBD)에 입각하여 파이로 안전조치 기술을 개발하고 있다. 한국원자력연구원은 파이로 안전조치접근방안 개발을 위한 IAEA 회원국지원프로그램(MSSP)을 수행하였다. IAEA 회원국 지원프로그램을 통하여 기준파이로시설(REPF) 개념을 설계하고, 이 시설에 대한 안전조치시스템을 개발하였다. 최근에 기준파이로시설은 용량이 증대된 REPF+로 업데이트 되고 있다. 핵물질계량관리시스템 성능평가를 위하여 전산코드 PYMUS를 개발하였으며, PYMUS는 전용탐지획률 통계평가 방안을 포함하여 업그레이드하고 있다. 파이로 입력물질 계량을 위한 비파괴분석장비로 ASNC가 개발되고 있으며, 파이로 출력물질인 U/TRU 잉곳을 계량하기위한 비파괴분석장비로 HIPAI가 개발되고 있다. 또한 컴프톤 억제 감마선분광기술, LIBS 기술, 균질화 공정의 샘플링 오차에 대한 평가도 진행 중이다. 이러한 노력들은 국내에서 선진핵주기기술 실현에 크게 기여할 것이다.
한국원자력연구원은 IAEA에서 권고하고 있는 안전조치기반설계(SBD)에 입각하여 파이로 안전조치 기술을 개발하고 있다. 한국원자력연구원은 파이로 안전조치접근방안 개발을 위한 IAEA 회원국지원프로그램(MSSP)을 수행하였다. IAEA 회원국 지원프로그램을 통하여 기준파이로시설(REPF) 개념을 설계하고, 이 시설에 대한 안전조치시스템을 개발하였다. 최근에 기준파이로시설은 용량이 증대된 REPF+로 업데이트 되고 있다. 핵물질계량관리시스템 성능평가를 위하여 전산코드 PYMUS를 개발하였으며, PYMUS는 전용탐지획률 통계평가 방안을 포함하여 업그레이드하고 있다. 파이로 입력물질 계량을 위한 비파괴분석장비로 ASNC가 개발되고 있으며, 파이로 출력물질인 U/TRU 잉곳을 계량하기위한 비파괴분석장비로 HIPAI가 개발되고 있다. 또한 컴프톤 억제 감마선분광기술, LIBS 기술, 균질화 공정의 샘플링 오차에 대한 평가도 진행 중이다. 이러한 노력들은 국내에서 선진핵주기기술 실현에 크게 기여할 것이다.
The Korea Atomic Energy Research Institute (KAERI) has developed a safeguards technology for pyroprocessing based on the Safeguards-By-Design (SBD) concept. KAERI took part in a Member-State Support Program (MSSP) to establish a pyroprocessing safeguards approach. A Reference Engineering-scale Pyrop...
The Korea Atomic Energy Research Institute (KAERI) has developed a safeguards technology for pyroprocessing based on the Safeguards-By-Design (SBD) concept. KAERI took part in a Member-State Support Program (MSSP) to establish a pyroprocessing safeguards approach. A Reference Engineering-scale Pyroprocessing Facility (REPF) concept was designed on which KAERI developed its safeguards system. Recently the REPF is being upgraded to the REPF+, a scaled-up facility. For assessment of the nuclear-material accountancy (NMA) system, KAERI has developed a simulation program named Pyroprocessing Material Flow and MUF Uncertainty Simulation (PYMUS). The PYMUS is currently being upgraded to include a Near-Real-Time Accountancy (NRTA) statistical analysis function. The Advanced Spent Fuel Conditioning Process Safeguards Neutron Counter (ASNC) has been updated as Non-Destructive Assay (NDA) equipment for input-material accountancy, and a Hybrid Induced-fission-based Pu-Accounting Instrument (HIPAI) has been developed for the NMA of uranium/transuranic (U/TRU) ingots. Currently, performance testing of Compton-suppressed Gamma-ray measurement, Laser-Induced Breakdown Spectroscopy (LIBS), and homogenization sampling are underway. These efforts will provide an essential basis for the realization of an advanced nuclear-fuel cycle in the ROK.
The Korea Atomic Energy Research Institute (KAERI) has developed a safeguards technology for pyroprocessing based on the Safeguards-By-Design (SBD) concept. KAERI took part in a Member-State Support Program (MSSP) to establish a pyroprocessing safeguards approach. A Reference Engineering-scale Pyroprocessing Facility (REPF) concept was designed on which KAERI developed its safeguards system. Recently the REPF is being upgraded to the REPF+, a scaled-up facility. For assessment of the nuclear-material accountancy (NMA) system, KAERI has developed a simulation program named Pyroprocessing Material Flow and MUF Uncertainty Simulation (PYMUS). The PYMUS is currently being upgraded to include a Near-Real-Time Accountancy (NRTA) statistical analysis function. The Advanced Spent Fuel Conditioning Process Safeguards Neutron Counter (ASNC) has been updated as Non-Destructive Assay (NDA) equipment for input-material accountancy, and a Hybrid Induced-fission-based Pu-Accounting Instrument (HIPAI) has been developed for the NMA of uranium/transuranic (U/TRU) ingots. Currently, performance testing of Compton-suppressed Gamma-ray measurement, Laser-Induced Breakdown Spectroscopy (LIBS), and homogenization sampling are underway. These efforts will provide an essential basis for the realization of an advanced nuclear-fuel cycle in the ROK.
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가설 설정
2) The powder heterogeneity between CuO/NiO powder and spent fuel powder is same even though theoretically spent fuel powder can be more heterogeneous than CuO/NiO powder because of a higher density of spent fuel powder. 3) The distribution of Pu concentration in spent fuel powder after decladding and low temperature oxidation process is same with the distribution of Pu concentration in a spent fuel rod. Pu mass in a 1g sample is ∑(mp × ρPu), in which mp is each spent fuel particle mass (or mass of each mass fraction group) and ρPu is the Pu concentration of each powder particle, thus as shown in Fig.
제안 방법
The goal of the safeguards system design is effective and efficient implementation of the safeguards to meet the IAEA technical objectives, and the safeguards system can be assessed by estimating the MUF uncertainty or Pu diversion detection probability of the NMA system. The precise input material accountancy is very important to the effectiveness of the safeguards, and the NDA technologies such as ASNC, HIPAI, and Compton-suppressed gamma-ray measurement system are very important to the efficiency of the safeguards system.
대상 데이터
3 shows the prototype HIPAI. It was fabricated using 6 3He tubes, and its performance was evaluated using AmLi, PuBe, 252Cf, and Pu sources. The measurement results were also shown in Fig.
데이터처리
45 um CuO and NiO powder were charged into each mixer, and mixed for several hours. 1 g samples were taken at each hour, and the uncertainty of the powder mass ratio was analyzed by Inductively Coupled Plasma Optical Emission Spectrometry (ICP-OES) whose instrumental uncertainty was 0.5% in ANOVA analysis. The analyzed results are shown in Fig.
성능/효과
6, the distribution of Pu concentration of a 59 GWd/tU spent fuel was calculated using a rod axial gamma scan profile and a RAPID program to simulate burn-up, U, and Pu contents in a radial direction. In this calculation, there are three assumptions; 1) The size of all powder particles is same about 45 um after mechanical decladding and low temperature oxidation, or small difference of powder particle size does not affect on mixing performance. 2) The powder heterogeneity between CuO/NiO powder and spent fuel powder is same even though theoretically spent fuel powder can be more heterogeneous than CuO/NiO powder because of a higher density of spent fuel powder.
In this calculation, there are three assumptions; 1) The size of all powder particles is same about 45 um after mechanical decladding and low temperature oxidation, or small difference of powder particle size does not affect on mixing performance. 2) The powder heterogeneity between CuO/NiO powder and spent fuel powder is same even though theoretically spent fuel powder can be more heterogeneous than CuO/NiO powder because of a higher density of spent fuel powder. 3) The distribution of Pu concentration in spent fuel powder after decladding and low temperature oxidation process is same with the distribution of Pu concentration in a spent fuel rod.
참고문헌 (13)
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