TY - GEN
T1 - US department of energy's codcon project an aqueous safeguards R&D program
AU - Bresee, James C.
AU - Paviet, Patricia D.
AU - Todd, Terry A.
N1 - Publisher Copyright:
Copyright © 2017 ASME.
PY - 2017
Y1 - 2017
N2 - In 2015, Office of Nuclear Energy of the U.S. Department of Energy established a research and development project at Pacific Northwest National Laboratory to evaluate the process control capability to produce a specific uranium/plutonium product from used commercial nuclear fuel using an aqueous codecontamination separations process. The process is controlled using on-line instrumentation supported by a dynamic process model. The new program is called the CoDCon project. The result of the study will be a quantitative measure of the current capability to produce a specific U/Pu product, using U-IV to reduce plutonium to Pu-III and prepare a mixed product, the composition predicted by a dynamic model, measured with on-line instrumentation and controlled by the adjustment of process variables. This approach would be an alternative to the use of the PUREX aqueous separations process that produces separate plutonium and uranium products that are later blended to prepare the desired mixture. Since plutonium is always accompanied by uranium, the project will provide a safeguards-by-design tool for possible use in future commercial separations plant designs. The effectiveness of the design tool will be quantified using a methodology published by B. Cipiti, et al1. The paper describes the process and the control system used by the project and provides details on the current status of the research and development program.
AB - In 2015, Office of Nuclear Energy of the U.S. Department of Energy established a research and development project at Pacific Northwest National Laboratory to evaluate the process control capability to produce a specific uranium/plutonium product from used commercial nuclear fuel using an aqueous codecontamination separations process. The process is controlled using on-line instrumentation supported by a dynamic process model. The new program is called the CoDCon project. The result of the study will be a quantitative measure of the current capability to produce a specific U/Pu product, using U-IV to reduce plutonium to Pu-III and prepare a mixed product, the composition predicted by a dynamic model, measured with on-line instrumentation and controlled by the adjustment of process variables. This approach would be an alternative to the use of the PUREX aqueous separations process that produces separate plutonium and uranium products that are later blended to prepare the desired mixture. Since plutonium is always accompanied by uranium, the project will provide a safeguards-by-design tool for possible use in future commercial separations plant designs. The effectiveness of the design tool will be quantified using a methodology published by B. Cipiti, et al1. The paper describes the process and the control system used by the project and provides details on the current status of the research and development program.
UR - https://www.scopus.com/pages/publications/85032566378
U2 - 10.1115/ICONE25-67965
DO - 10.1115/ICONE25-67965
M3 - Conference contribution
AN - SCOPUS:85032566378
SN - 9784888982566
T3 - International Conference on Nuclear Engineering, Proceedings, ICONE
BT - Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events
PB - American Society of Mechanical Engineers (ASME)
T2 - 2017 25th International Conference on Nuclear Engineering, ICONE 2017
Y2 - 2 July 2017 through 6 July 2017
ER -