Technical basis for storage of Zircaloy-clad spent fuel in inert gases

Johnson, A.B.; Gilbert, E.R.

doi:10.2172/713558

Cited by 32 publications

(21 citation statements)

References 5 publications

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“…• C to avoid controversies [8]. Once sealed in the canister, there is no possibility of monitoring the evolution of the fuel assembly inside the canister, and to verify the state, the canister has to be opened.…”

Section: Behaviour Of Spent Fuel Assembliesmentioning

confidence: 99%

Ageing management program for the Spanish low and intermediate level waste disposal and spent fuel and high-level waste centralised storage facilities

Zuloaga

Ordoñez

Andrade

et al. 2011

EPJ Web of Conferences

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Abstract. The generic design of the centralised spent fuel storage facility was approved by the Spanish Safety Authority in 2006. The planned operational life is 60 years, while the design service life is 100 years. Durability studies and surveillance of the behaviour have been considered from the initial design steps, taking into account the accessibility limitations and temperatures involved. The paper presents an overview of the ageing management program set in support of the Performance Assessment and Safety Review of El Cabril low and intermediate level waste (LILW) disposal facility. Based on the experience gained for LILW, ENRESA has developed a preliminary definition of the Ageing Management Plan for the Centralised Interim Storage Facility of spent Fuel and High Level Waste (HLW), which addresses the behaviour of spent fuel, its retrievability, the confinement system and the reinforced concrete structure. It includes tests plans and surveillance design considerations, based on the El Cabril LILW disposal facility.

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Section: Behaviour Of Spent Fuel Assembliesmentioning

confidence: 99%

Ageing management program for the Spanish low and intermediate level waste disposal and spent fuel and high-level waste centralised storage facilities

Zuloaga

Ordoñez

Andrade

et al. 2011

EPJ Web of Conferences

View full text Add to dashboard Cite

show abstract

“…In this worst case scenario, the temperature might be sufficiently high and the oxygen sufficiently plentiful for the spent fuel cladding to fail 10 . Cladding failure would, in turn, cause oxidation of the UO 2 fuel to U 3 O 8 which would result in splitting of the cladding and crumbling of the pellets into powder.…”

Section: Projection Of Operating Environment For Waste Package Basketmentioning

confidence: 99%

Scoping corrosion tests on candidate waste package basket materials for the Yucca Mountain Project

Konynenburg¹,

Curits²,

Summers³

1998

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S.E. Summers March 1998This is an informal report intended primarily for internal or limited external distribution. The opinions and conclusions stated are those of the author and may or may not be those of the Laboratory. Work performed under the auspices of the U.S. Department of Energy by the Lawrence Livermore National Laboratory under Contract W-7405-ENG-48. DISCLAIMERThis document was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor the University of California nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or the University of California. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or the University of California, and shall not be used for advertising or product endorsement purposes.This report has been reproduced directly from the best available copy. i Abstract A scoping corrosion test was performed on candidate waste package basket materials. The corrosion medium was a pH-buffered solution of chemical species expected to be produced by radiolysis. The test was conducted at 90°C for 96 hours. Samples included aluminum-, copper-, stainless steel-and zirconium-based metallic materials and several ceramics, incorporating neutron-absorbing elements. Sample weight losses and solution chemical changes were measured. Both corrosion of the host materials and dissolution of the neutron-absorbing elements were studied. The ceramics and the zirconium-based materials underwent only minor corrosion. The stainless steel-based materials performed well except for a welded sample. The aluminum-and copper-based materials exhibited the highest corrosion rates. Boron dissolution depends on its chemical form. Boron oxide and many metal borides dissolve readily in acidic solutions while high-chromium borides and boron carbide, though thermodynamically unstable, exhibit little dissolution in short times. The results of solution chemical analyses were consistent with this. Gadolinium did not dissolve significantly from monazite, and hafnium showed little dissolution from a variety of host materials, in keeping with its low solubility.

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“…The release of 85Kr to the cask was essentiallylinear during the 2.5 months of testing and indicatesthat the defect in the cladding was very small. The krypton releases during the REA 2023 cask test are compared in Figure 3.6 with the 85Kr releases observed in assembly B02 in the Fuel Temperature Test (FTT)(Johnson and Gilbert 1983) that was conducted to assess dry storage of spent fuel. The backgroundlevel (3.086 x°I0-8 Ci) in the FTT, I% release of the 85Kr produced in a single fuel rod, and 20% release of the 85Kr produced in a single fuel rod are plotted inFigure 3…”

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confidence: 99%

Spent nuclear fuel storage -- Performance tests and demonstrations

McKinnon¹,

DeLoach²

1993

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This report summarizes the results of heat transfer and shielding performance tests and demonstrations conducted from 1983 through 1992 by or in cooperation with the U. S. Department of Energy (DOE), Office of Commercial Radioactive Waste Management (OCRWM). The performance tests cor,sisted of 6 to tions was estimated to be extremely small, and has had no adverse effect on testing efforts. iii ACRONYMS AND INITIALISMS BWR boil ing water reactor CCP

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Technical basis for storage of Zircaloy-clad spent fuel in inert gases

Cited by 32 publications

References 5 publications

Ageing management program for the Spanish low and intermediate level waste disposal and spent fuel and high-level waste centralised storage facilities

Ageing management program for the Spanish low and intermediate level waste disposal and spent fuel and high-level waste centralised storage facilities

Scoping corrosion tests on candidate waste package basket materials for the Yucca Mountain Project

Spent nuclear fuel storage -- Performance tests and demonstrations

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