干旱区生态环境知识资源中心(Arid): Viability Study for an Unattended UF<sub>6</sub> Cylinder Verification Station: Phase I Final Report

Arid

DOI	10.2172/1333456
报告编号	PNNL--25395
来源ID	OSTI_ID: 1333456
	Viability Study for an Unattended UF₆ Cylinder Verification Station: Phase I Final Report
	Smith, Leon E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)]; Miller, Karen A. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)]; Garner, James R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)]; Branney, Sean [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)]; McDonald, Benjamin S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)]; Webster, Jennifer B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)]; Zalavadia, Mital A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)]; Todd, Lindsay C. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)]; Kulisek, Jonathan A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)]; Nordquist, Heather [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)]; Deshmukh, Nikhil S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)]; Stewart, Scott [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)]
英文摘要	In recent years, the International Atomic Energy Agency (IAEA) has pursued innovative techniques and an integrated suite of safeguards measures to address the verification challenges posed by the front end of the nuclear fuel cycle. Among the unattended instruments currently being explored by the IAEA is an Unattended Cylinder Verification Station (UCVS) that could provide automated, independent verification of the declared relative enrichment, ²³⁵U mass, total uranium mass and identification for all declared UF₆ cylinders in a facility (e.g., uranium enrichment plants and fuel fabrication plants). Under the auspices of the United States and European Commission Support Programs to the IAEA, a project was undertaken to assess the technical and practical viability of the UCVS concept. The US Support Program team consisted of Pacific Northwest National Laboratory (PNNL, lead), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL) and Savanah River National Laboratory (SRNL). At the core of the viability study is a long-term field trial of a prototype UCVS system at a Westinghouse fuel fabrication facility. A key outcome of the study is a quantitative performance evaluation of two nondestructive assay (NDA) methods being considered for inclusion in a UCVS: Hybrid Enrichment Verification Array (HEVA), and Passive Neutron Enrichment Meter (PNEM). This report provides context for the UCVS concept and the field trial: potential UCVS implementation concepts at an enrichment facility; an overview of UCVS prototype design; field trial objectives and activities. Field trial results and interpretation are presented, with a focus on the performance of PNEM and HEVA for the assay of over 200 鈥渢ypical鈥?Type 30B cylinders, and the viability of an 鈥淣DA Fingerprint鈥?concept as a high-fidelity means to periodically verify that the contents of a given cylinder are consistent with previous scans. A modeling study, combined with field-measured instrument uncertainties, provides an assessment of the partial-defect sensitivity of HEVA and PNEM for both one-time assay and (repeated) NDA Fingerprint verification scenarios. The findings presented in this report represent a significant step forward in the community鈥檚 understanding of the strengths and limitations of the PNEM and HEVA NDA methods, and the viability of the UCVS concept in front-end fuel cycle facilities. This experience will inform Phase II of the UCVS viability study, should the IAEA pursue it.
出版年	2016
报告类型	Technical Report
语种	英语
国家	美国
来源学科分类	98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION ; 42 ENGINEERING ; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS ; URANIUM HEXAFLUORIDE ; VERIFICATION ; URANIUM ; CYLINDERS ; ISOTOPE SEPARATION PLANTS ; URANIUM 235 ; ENRICHMENT ; FUEL FABRICATION PLANTS ; MASS ; PERFORMANCE ; DEFECTS ; DESIGN ; EVALUATION ; NONDESTRUCTIVE ANALYSIS ; IMPLEMENTATION ; IAEA SAFEGUARDS ; SENSITIVITY ; SIMULATION ; IDENTIFICATION SYSTEMS ; FEASIBILITY STUDIES
URL	http://www.osti.gov/scitech/servlets/purl/1333456
资源类型	科技报告
条目标识符	http://119.78.100.177/qdio/handle/2XILL650/271318
推荐引用方式 GB/T 7714	Smith, Leon E. [Pacific Northwest National Lab. ,Miller, Karen A. [Los Alamos National Lab. ,Garner, James R. [Oak Ridge National Lab. ,et al. Viability Study for an Unattended UF₆ Cylinder Verification Station: Phase I Final Report,2016.