14b. J u s t i f i c a t i o n D e t a i l s A r e v i s i o n t o t h e system design d e s c r i p t i o n was r e q u i r e d because o f changes i n t h e design o f t h e MkI l i d removal t o o l s .2. ECN Abstract: This System Design Description provides: (1) statements of the Spent Nuclear Fuel Project's needs for sampling o f fuel in the K East and K West Basins, (2) the sampling equipment functions and requirements, (3) a general work plan and the design logic followed to develop the equipment, and (4) a summary description o f the design for the sampling equipment. This report summarizes the integrated application o f both the subject equipment and the canister sludge sampling system in the characterization campaigns at K Basins. -updated s e c t i o n s 4.0 and 5.0 t o r e f l e c t I I chanqes i n t h e design o f t h e MkI l i d I n i t i a l Revision, Approval EDT 610195 dated February 9, 1996. Other Affected Documents: (NOTE: Documents l i s t e d below w i l l not be revised by t h i s ECN.) Signatures below i n d i c a t e t h a t the signing organization has been n o t i f i e d o f other affected documents1 be Suoerseded r e v . 0 Der ECN 605796 w i t h t h e removal t o o l s .-added drawing l i s t and support equipment sketches t o Appendix A and d e l e t e d r e f e r e n c e copies o f MkI t o o l drawings.-added Appendices B and C t o p r o v i d e a l i s t o f supporting documentation and o p e r a t i n g procedures associated w i t h t h e sampling equipment.
SummaryAn N-Reactor inner element that had been stored underwater in the Hanford 1 OO-Area K-West Basin was subjected to a combination of low-and high-temperature vacuum drying treatments. These studies are part of a series of tests being conducted by Pacific Northwest National Laboratory on the drying behavior of spent nuclear fuel (SNF) elements removed from both the K-West and K-East Basins.The drying test series was designed to test fuel elements that ranged from intact to severely damaged.The fuel element discussed here was removed from K-West canister 1990 during the f i r s t fuel selection campaign conducted in 1995. Visual inspection of this fuel element indicated that it was likely intact, having only a small dent or chip at one end. The element has remained in wet storage in the Postirradiation Testing Laboratory (PTL, 327 Building) since that time.The drying test was conducted in the Whole Element Furnace Testing System located in G-Cell within the PTL. The furnace testing system is composed of three basic systems: the in-celi furnace equipment, the system gas loop, and the analytical instrument package. Element 1990 was subjected to drying processes proposed under the Integrated Process Strategy, which included a hot drying step. The testing cycles are listed below:Cold Vacuum Drying (CVD) at 5OoC under vacuum for approximately 8 hr Pressure Rise Test under static low-pressure conditions at 50°C for 1 hr Gas Evolution Test at 75OC, at near-atmospheric pressure, using an argon background gas for approximately 12 hr Hot Vacuum Drying (HVD) at 3OOOC under vacuum for a total of 120 hr (24 hr for heatup to 3OOOC at atmospheric pressure, followed by 96 hr at 300°C) Water Removal Verification Test at 425°C under vacuum for 6 hr System cooIdown to ambient conditions. The removal of free water in the system during the CVD process was not complete. During the Pressure Rise Test and Gas Evolution Test, measurable amounts of water were detected by the moisture probe, representing the remaining free water in the system. The water that was not released during CVD is consistent with evaporation from surface films on the element and on the heated inner surfaces of the furnace.The Pressure Rise Test in vacuum showed a linear pressure rise with time at constant temperature. The moisture release kinetics are, therefore, independent of concentration of moisture in the system (Le., a zeroth order reaction). The atmosphere of the system was far removed from saturation, thereby providing ... 111an unlimited sink for water molecule release. The linear release, and the small quantity of moisture evolved, suggests partial evaporation of a surface film of one or more monolayers.Thermal decomposition of hydrated species was the most significant factor in controlling the removal of water from the system during the HVD. Gas flow and vacuum condition may be secondary factors in the process of drying the SNF element. A temperature above 300°C may be required for complete drying of the hydrated species within a reasonable period of...
SummaryThis document provides a detailed description of the Hanford Spent Nuclear Fuel (SNF) Whole Element Furnace Testing System located in the Postirradiation Testing Laboratory G-Cell (327 Building). Equipment specifications, system schematics, general operating modes, maintenmce and calibration requirements, and other supporting information are provided in this document. This system was developed for performing cold vacuum drying and hot vacuum drying testing of whole N-Reactor fuel elements, which were sampled from the 105-K East and K West Basins. The proposed drying processes are intended to allow dry storage of the SNF for long periods of time. The furnace testing system is used to evaluate these processes by simulating drying sequences with a single fuel element and measuring key system parameters such as internal pressures, temperatures, moisture levels, and off-gas composition.... 111 Quality AssuranceThis work was conducted under the Quality Assurance Program, Pacific Northwest National Laboratory (PNNL) SNF-70-001, SNF Qualily Assurance Program, as implemented by the PNNL SNF effectively implement the requirements of DOE/RW-O333P, Office of Civilian Radioactive Waste Management Quality Assurance Requirements and Description (QARO), Compliance with the QARD requirements is mandatory for projects which generate data used to support the development of a permanent High-Level Nuclear Waste repository. Further, the U.S. Department of Energy has determined that the testing activities which generated the results documented in this report shall comply with the QARD. Supporting records for the data in this report are located in the permanent PNNL SNF
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