초록 ▼

본 감손우라늄폐기물 부피감용 공학기술 개발과제에서는 민간분야에서 발생하였지만 국가적 관심이 된 난 처리성 우라늄 폐촉매 처리 실용화 기술을 개발하기 위하여 원자력연구원에서 개발한 우라늄 폐촉매 처리 특허 기술의 공학적(pilot) 검증 및 실용화를 위하여 감손우라늄폐기물 부피감용 장치의 제작설치 및 운전평가 관련 pilot 실증 실험을 평가하였으며, 과제의 목표인 우라늄폐촉매 부피감용율 50% 이상, 자체처분 될 SiO₂ 케익의 방사능 농도 1 Bq/g 이하 및 최종 방류수의 우라늄 농도 1 ppm 미만을 pil

본 감손우라늄폐기물 부피감용 공학기술 개발과제에서는 민간분야에서 발생하였지만 국가적 관심이 된 난 처리성 우라늄 폐촉매 처리 실용화 기술을 개발하기 위하여 원자력연구원에서 개발한 우라늄 폐촉매 처리 특허 기술의 공학적(pilot) 검증 및 실용화를 위하여 감손우라늄폐기물 부피감용 장치의 제작설치 및 운전평가 관련 pilot 실증 실험을 평가하였으며, 과제의 목표인 우라늄폐촉매 부피감용율 50% 이상, 자체처분 될 SiO₂ 케익의 방사능 농도 1 Bq/g 이하 및 최종 방류수의 우라늄 농도 1 ppm 미만을 pilot 규모에서도 충분히 만족하였으며, 공학 규모 처리시설의 설계, 핵물질 취급 인허가 등의 법적요건과 감손우라늄폐기물 부피감용 장치 제작/설치, 장치 운영 최적화를 통해 본 과제에서 얻어지는 기술을 기반으로 상용화 시 활용되어질 예정이다.

(출처 : 보고서 요약서 3p)

Abstract ▼

Ⅳ. Result of Project
1) Section 1. Research contents carried out in the 1^st year

○ Preparation of engineering scale processing facility design data and construction of safety facility
In order to construct a treatment facility for volume reduction of uranium waste catalyst, t

Ⅳ. Result of Project
1) Section 1. Research contents carried out in the 1^st year

○ Preparation of engineering scale processing facility design data and construction of safety facility
In order to construct a treatment facility for volume reduction of uranium waste catalyst, the conceptual design of the treatment facility and the legal requirements were examined. As a result, the facility is allowed to use the fuel material in accordance with Article 45 of the Nuclear Safety Act and at the same time transfer the nuclear fuel material to be studied after the approval of the measuring management provision. Therefore, this facility is designed to comply with legal requirements based on the Nuclear Safety Act. Permission to use the facility has been approved by the Yuseong District Office of Daejeon Metropolitan City.

○ License for handling nuclear material
The license for the use of nuclear fuel materials was submitted in April 2016 and received a license to use nuclear fuel materials from the Nuclear Safety Commission in July. In addition, the application for the approval of the nuclear substance measuring management provision was also submitted to the Nuclear Safety Commission in July 2016 and approved in August.
There are required technical standards for nuclear fuel material facilities in Nuclear Safety Act article 45, article 69 of the Enforcement Decree, Enforcement Rule 53, Rules 4 and 5 of technical standards on radiation safety management. License was obtained by satisfying the requirements regarding drainage and exhaust facilities, fire-resistant facilities, and facility improvement for contamination prevention.

2) Section 2. Research contents carried out in the 2^nd year

○ Pilot-scale DU waste volume reduction facility design, production and installation
The pilot-scale DU waste volume reduction process is based on lab-scale/bench-scale process and consists of Si dissolution and solid-liquid separation process, SiO₂ precipitation and purification process, and UPO₄ precipitation process. Pipes and valves connected with each volume device were carefully examined and fabricated and installed.
In order to evaluate the performance of the device and to master the operation, the optimum operation condition was derived by using the results of the trial run and evaluation.
In the test evaluation of 630 ㎜ Filter Press (F1) for solid-liquid separation, solid-liquid separation was performed using Kaolin instead of U-free TK-1. In the test evaluation of 630 ㎜ Filter Press (F2) for separation of Si (silica) cake, the test was performed using fumed silica to confirm Si (silica) cake formation.

○ Pilot-scale DU waste volume reduction facility operation evaluation
Through the joint operation evaluation of the pilot-scale process and the technical demonstration of each unit process, results were obtained as follows. The volume reduction rate (%) by solid-liquid separation after Si dissolution is 50% or more. The result of analysis of the uranium concentration of the silica cake, which is the self-disposal subject from the solid-liquid separation process, is 1 Bq/g or less. After the UPO₄ precipitation, the liquid process waste solution is less than 1 ppm. All the results comply with regulatory requirements. It would be more effective if the improvements derived from pilot-scale technology demonstration are reflected in commercialization in the future.

(출처 : SUMMARY 8p)

목차 Contents

• 표지 ... 1
• 제 출 문 ... 2
• 보고서 요약서 ... 3
• 요 약 문 ... 4
• SUMMARY ... 7
• CONTENTS ... 11
• 목차 ... 15
• 표목차 ... 19
• 그림목차 ... 21
• 제1장 연구개발과제의 개요 ... 26
• 제2장 국내외 기술개발 현황 ... 32
• 제 1 절 세계 수준 ... 34
• 제 2 절 국내 수준 ... 34
• 제 3 절 국내외 연구현황 ... 36
• 제3장 연구개발수행 내용 및결과 ... 38
• Task 1 공학규모 처리시설 설계자료 작성 및 안전시설구축 ... 40
• Task 2 핵연료물질 사용(취급) 인허가 ... 64
• TASK 3 공학규모 감손우라늄폐기물 부피감용 공정장치 제작 설치 ... 75
• TASK 4 공학규모 감손우라늄폐기물 부피감용 공정장치 운전평가 ... 121
• 제4장 목표달성도 및관련분야에의 기여도 ... 140
• 제 1 절 목표 달성도 ... 142
• 제 2 절 대외기여도 ... 142
• 제5장 연구개발의 활용 계획 ... 144
• 제6장 연구개발과정에서수집한 해외과학기술정보 ... 148
• 제7장 연구개발성과의 보안등급 ... 152
• 제8장 연구장비의 구축및 활용결과 ... 156
• 제9장 연구개발 수행에 따른연구실 동의 안전 조치이행 실적 ... 160
• 제10장 부록 ... 164
• 끝페이지 ... 168