Post Irradiation Examination Plan for High-Burnup Demonstration Project Sister Rods

Scaglione, John M; Montgomery, Rose; Bevard, Bruce Balkcom

doi:10.2172/1248793

Cited by 7 publications

(9 citation statements)

References 4 publications

(6 reference statements)

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“…The DEs are performed using a phased approach, as described by Saltzstein [2]. This report documents the status of the ORNL Phase 1 DEs, outlines the DE tasks performed, and documents the data collected to date, as guided by the sister rod test plans [2,3]. Testing is performed and documented per the requirements of the ORNL sister rod test plan [3], which includes applicable consensus standards (e.g., American Society for Testing and Materials), regulatory requirements (e.g., DOE orders), and adherence to the laboratory and Fuel Cycle Technologies quality assurance plans.…”

Section: List Of Tablesmentioning

confidence: 99%

Sister Rod Destructive Examinations (FY2021)

Montgomery¹,

Bevard²

2022

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This report documents work performed under the Spent Fuel and Waste Disposition's Spent Fuel and Waste Science and Technology program for the US Department of Energy (DOE) Office of Nuclear Energy (NE). This work was performed to fulfill Level 2 Milestone M2SF-22OR010201042, "FY2021 ORNL Report on High Burnup Sibling Pin Testing Results," within work package SF-22OR01020104 and is an update to the work reported in M2SF-21OR010201032, M2SF-19ORO010201026 and M2SF-19OR010201028. Sister Rod Destructive Examinations March 31, 2022 v Planned DE Status / Applicable Appendix Comments Five more tests with unpressurized specimens are expected to be completed in FY22. Tests using pressurized segments are planned to follow the unpressurized tests. DE.01 Measure internal pressure of five baseline and three heattreated rods Complete / Appendix CThe rod internal pressure and the void volume available inside the rod were measured for eight sister rods at room temperature (RT), and all pressures are within the publicly available database envelope. There is a clear correlation between the post-irradiated rod internal pressure and the as-designed fill pressure. The fission gas partial pressure trends well with the rod average burnup. The pressure and void volumes measured are consistent for rods from the same fuel vendor. The product of the partial pressure of the fission gas and the void volume, P f V, is consistent from lab to lab for sister rods from the same assembly, except for the two rods from assembly F35. A comparison of P f V indicates that the ZIRLO-clad rods might have experienced some change in pressure, void volume, or both due to the heat treatment applied, but the M5-clad rods do not exhibit the same effects.Comparisons with predictions from fuel rod performance codes FAST and BISON indicate a tendency for FAST to underpredict pressure and BISON to overpredict pressure.

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Section: List Of Tablesmentioning

confidence: 99%

Sister Rod Destructive Examinations (FY2021)

Montgomery¹,

Bevard²

2022

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“…June 2018 Figure 10. Gamma count on high burnup PWR fuel rod, showing that the burnup is relatively stable between spacers [11].…”

Section: Rod Characterization and Re-fabricationmentioning

confidence: 99%

In-cell Re-fabrication and Loss-of-coolant Accident (LOCA) Testing of High Burnup Commercial Spent Fuel

Raftery

Yan

Smith

et al. 2018

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A high burnup commercial spent fuel segment was re-fabricated into a pressurized test train for fuel safety testing in the Irradiated Fuels and Examination Laboratory (IFEL) hot cell facility at Oak Ridge National Laboratory. Descriptions of the in-cell re-fabrication capabilities and assembly of the loss-ofcoolant-accident (LOCA) test train are provided. An in-cell integral LOCA test was performed in the Severe Accident Test Station (SATS) by subjecting the fuel segment to a steam environment, internal pressure, temperatures up to 1200ºC, and water quench. The successful in-cell re-fabrication and integral LOCA demonstration test restores a domestic capability for out-of-pile integral fuel safety testing. In addition, this work establishes the SATS system as a vital tool for evaluation of commercial spent fuel and future accident tolerant fuel (ATF) concepts subject to design basis accident (DBA) and beyond design basis accident (BDBA) scenarios. In-cell Re-fabrication and Loss-of-coolant Accident (LOCA) Testing of High Burnup Commercial Spent Fuel vi

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“…This section provides a general description of each set of rods from the Post Irradiation Examination Plan for High-Burnup Demonstration Project Sister Rods [7], [8]. Some additional information comes from an updated draft of this same document [9].…”

Section: Details Of Scanned Spent Nuclear Fuel Rodsmentioning

confidence: 99%

“…The information in this section is provided by and sometimes paraphrased from References[7],[8], and[9].…”

mentioning

confidence: 99%

High-resolution Gamma Spectroscopy Measurements of Pressurized Water Reactor Spent Nuclear Fuel Rods

Smith

Nicholson

Croft

et al. 2018

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Post Irradiation Examination Plan for High-Burnup Demonstration Project Sister Rods

Cited by 7 publications

References 4 publications

Sister Rod Destructive Examinations (FY2021)

Sister Rod Destructive Examinations (FY2021)

In-cell Re-fabrication and Loss-of-coolant Accident (LOCA) Testing of High Burnup Commercial Spent Fuel

High-resolution Gamma Spectroscopy Measurements of Pressurized Water Reactor Spent Nuclear Fuel Rods

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