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Dive into the research topics where Guillermo D DelCul is active.

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Featured researches published by Guillermo D DelCul.


Archive | 2016

Complete Non-Radioactive Operability Tests for Cladding Hull Chlorination

Emory D Collins; Jared A. Johnson; Tom D. Hylton; Ronald Ray Brunson; Rodney D. Hunt; Guillermo D DelCul; Eric Craig Bradley; Barry B. Spencer

Non-radioactive operability tests were made to test the metal chlorination reactor and condenser and their accessories using batch chlorinations of non-radioactive cladding samples and to identify optimum operating practices and components that need further modifications prior to installation of the equipment into the hot cell for tests on actual used nuclear fuel (UNF) cladding. The operability tests included (1) modifications to provide the desired heating and reactor temperature profile; and (2) three batch chlorination tests using, respectively, 100, 250, and 500 g of cladding. During the batch chlorinations, metal corrosion of the equipment was assessed, pressurization of the gas inlet was examined and the best method for maintaining solid salt product transfer through the condenser was determined. Also, additional accessing equipment for collection of residual ash and positioning of the unit within the hot cell were identified, designed, and are being fabricated.


Archive | 2016

Reaction System Design for NO2 Oxidation of Used Nuclear Fuel for the FY17 Hot Test

Jared A. Johnson; Guillermo D DelCul

A dry pretreatment process based on the oxidation of used nuclear fuel to convert it to a fine powder is being studied for the removal and capture of tritium and iodine before subsequent processing. The process converts oxide fuel into a fine powder at low temperature using NO2/O2 mixtures. The form of the powder product can be selected to be U3O8, UO3, or a nitrate by adjusting the processing conditions. All the fundamental tenets of the process have been successfully demonstrated as a proof of principle, and many aspects have been corroborated multiple times at laboratory scale. The present thrust is to develop the process to a technology-readiness level sufficient to evaluate and estimate the cost of an engineering-scale implementation. A previous roadmap analysis of the implementation determined that the most desirable approach would be based on kilogram-scale experiments using real fuel in parallel with multi-kg testing of prototype systems using surrogate material. Following the planned approach, kilogram-scale experiments will be conducted in FY 2017. This report describes the primary reaction system designs and the equipment that has been fabricated. Details related to instrumentation, data acquisition, and controls have been previously reported.


Archive | 2015

Zirconium Recycle Test Equipment for Hot Cell Operations

Emory D Collins; Guillermo D DelCul; Barry B. Spencer; Eric Craig Bradley; Ronald Ray Brunson

The equipment components and assembly support work were modified for optimized, remote hot cell operations to complete this milestone. The modifications include installation of a charging door, Swagelok connector for the off-gas line between the reactor and condenser, and slide valve installation to permit attachment/replacement of the product salt collector bottle.


Procedia Chemistry | 2012

Process Development Studies for Zirconium Recovery/Recycle from used Nuclear Fuel Cladding☆☆☆

Emory D Collins; Guillermo D DelCul; Barry B. Spencer; R.R. Brunson; Jared A. Johnson; D.S. Terekhov


Archive | 2013

Advanced dry head-end reprocessing of light water reactor spent nuclear fuel

Emory D Collins; Guillermo D DelCul; Rodney D. Hunt; Jared A. Johnson; Barry B. Spencer


Archive | 1978

Cermet high level waste forms

W Scott Aaron; Emory D Collins; Guillermo D DelCul; Robert Thomas Jubin; Raymond James Vedder


Archive | 2009

Analysis of the Reuse of Uranium Recovered from the Reprocessing of Commercial LWR Spent Fuel

Guillermo D DelCul; Lee Trowbridge; John-Paul Renier; Ronald James Ellis; Kent Williams; Barry B. Spencer; Emory D Collins


Archive | 2007

Preliminary Multicycle Transuranic Actinide Partitioning-Transmutation Studies

Emory D Collins; Guillermo D DelCul; John P. Renier; Barry B. Spencer


Archive | 2011

SUPPORTED LIQUID INORGANIC MEMBRANES FOR NUCLEAR WASTE SEPARATION

Ramesh R. Bhave; Melanie Moses Debusk; Guillermo D DelCul; Lætitia H. Delmau; Chaitanya K. Narula


Archive | 2010

A Practical Solution to Used Nuclear Fuel Treatment to Enable Sustained Nuclear Energy and Recovery of Vital Materials

Emory D Collins; Guillermo D DelCul; James E Rushton; Kent Williams

Collaboration


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Emory D Collins

Oak Ridge National Laboratory

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Barry B. Spencer

Oak Ridge National Laboratory

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Robert Thomas Jubin

Oak Ridge National Laboratory

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Dan W Ramey

Oak Ridge National Laboratory

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Rodney D. Hunt

Oak Ridge National Laboratory

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Eric Craig Bradley

Oak Ridge National Laboratory

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John-Paul Renier

Oak Ridge National Laboratory

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Kent Williams

Oak Ridge National Laboratory

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Tom D. Hylton

Oak Ridge National Laboratory

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