Characteristics and performance of zirlo cladding used fuel

Guirong Pan; Rose Montgomery; David B. Mitchell; Brady D. Hanson

Characteristics and performance of zirlo cladding used fuel

Guirong Pan, Rose Montgomery, David B. Mitchell, Brady D. Hanson

Used Fuel & Nuclear Material Disposition

Research output: Contribution to conference › Paper › peer-review

Abstract

As part of the “North Anna Sister Rods” program, some high burnup (HBU) ZIRLO^® clad fuel rods were shipped to Oak Ridge National Laboratory (ORNL). The Sister Rods project is supporting US Department of Energy (DOE)'s “High Burnup Spent Fuel Data Project”, focusing on “understanding the effects of long-term storage and transportation on high burnup (HBU) (>45 GWD/MTU) light water reactor fuel”. The ZIRLO rods from the Sister Rods program are representative of a majority of Westinghouse's used fuel with ZIRLO cladding with rod-average burnup ranging from 48 to 59 GWd/MTU and a standard 9.5 mm (0.374 inches) rod diameter in a 17×17 array. Some performance characteristics of the entire ZIRLO sister rods are being obtained at ORNL, including visual, axial growth and in-reactor corrosion. The rod internal pressure and fission gas release were obtained from both ORNL and PNNL (Pacific Northwest National Laboratory). The characteristics and performance of ZIRLO sister rods are being evaluated for transportation and interim/long term storage. The evaluation includes comparing the measurement data with historical databases as well as model predictions. This paper will report the evaluations of the characteristics and performance of ZIRLO sister rods for transportation and storage.

Original language	English
Pages	77-84
Number of pages	8
State	Published - 2020
Event	14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019 - Seattle, United States Duration: Sep 22 2019 → Sep 27 2019

Conference

Conference	14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019
Country/Territory	United States
City	Seattle
Period	09/22/19 → 09/27/19

Funding

The authors extend their gratitude to the utilities that are supporting the spent fuel study program by providing access to their reactors for post irradiation testing and by providing the spent fuel. The authors would also like to acknowledge the efforts of personnel at ORNL, PNNL and Studsvik Sweden for performing examinations in the hot cell and mechanical test lab.

Funders	Funder number
Oak Ridge National Laboratory
Pacific Northwest National Laboratory

Keywords

Characteristics
Dry storage
High burnup
Performance
Sister rods
Used nuclear fuel
ZIRLO cladding

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

Cite this

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title = "Characteristics and performance of zirlo cladding used fuel",

abstract = "As part of the “North Anna Sister Rods” program, some high burnup (HBU) ZIRLO{\textregistered} clad fuel rods were shipped to Oak Ridge National Laboratory (ORNL). The Sister Rods project is supporting US Department of Energy (DOE)'s “High Burnup Spent Fuel Data Project”, focusing on “understanding the effects of long-term storage and transportation on high burnup (HBU) (>45 GWD/MTU) light water reactor fuel”. The ZIRLO rods from the Sister Rods program are representative of a majority of Westinghouse's used fuel with ZIRLO cladding with rod-average burnup ranging from 48 to 59 GWd/MTU and a standard 9.5 mm (0.374 inches) rod diameter in a 17×17 array. Some performance characteristics of the entire ZIRLO sister rods are being obtained at ORNL, including visual, axial growth and in-reactor corrosion. The rod internal pressure and fission gas release were obtained from both ORNL and PNNL (Pacific Northwest National Laboratory). The characteristics and performance of ZIRLO sister rods are being evaluated for transportation and interim/long term storage. The evaluation includes comparing the measurement data with historical databases as well as model predictions. This paper will report the evaluations of the characteristics and performance of ZIRLO sister rods for transportation and storage.",

keywords = "Characteristics, Dry storage, High burnup, Performance, Sister rods, Used nuclear fuel, ZIRLO cladding",

author = "Guirong Pan and Rose Montgomery and Mitchell, {David B.} and Hanson, {Brady D.}",

note = "Publisher Copyright: Copyright {\textcopyright} GLOBAL 2019 - International Nuclear Fuel Cycle Conference and TOP FUEL 2019 - Light Water Reactor Fuel Performance Conference.All rights reserved.; 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019 ; Conference date: 22-09-2019 Through 27-09-2019",

year = "2020",

language = "English",

pages = "77--84",

}

Characteristics and performance of zirlo cladding used fuel. / Pan, Guirong; Montgomery, Rose; Mitchell, David B. et al.
2020. 77-84 Paper presented at 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019, Seattle, United States.

Research output: Contribution to conference › Paper › peer-review

TY - CONF

T1 - Characteristics and performance of zirlo cladding used fuel

AU - Pan, Guirong

AU - Montgomery, Rose

AU - Mitchell, David B.

AU - Hanson, Brady D.

PY - 2020

Y1 - 2020

N2 - As part of the “North Anna Sister Rods” program, some high burnup (HBU) ZIRLO® clad fuel rods were shipped to Oak Ridge National Laboratory (ORNL). The Sister Rods project is supporting US Department of Energy (DOE)'s “High Burnup Spent Fuel Data Project”, focusing on “understanding the effects of long-term storage and transportation on high burnup (HBU) (>45 GWD/MTU) light water reactor fuel”. The ZIRLO rods from the Sister Rods program are representative of a majority of Westinghouse's used fuel with ZIRLO cladding with rod-average burnup ranging from 48 to 59 GWd/MTU and a standard 9.5 mm (0.374 inches) rod diameter in a 17×17 array. Some performance characteristics of the entire ZIRLO sister rods are being obtained at ORNL, including visual, axial growth and in-reactor corrosion. The rod internal pressure and fission gas release were obtained from both ORNL and PNNL (Pacific Northwest National Laboratory). The characteristics and performance of ZIRLO sister rods are being evaluated for transportation and interim/long term storage. The evaluation includes comparing the measurement data with historical databases as well as model predictions. This paper will report the evaluations of the characteristics and performance of ZIRLO sister rods for transportation and storage.

AB - As part of the “North Anna Sister Rods” program, some high burnup (HBU) ZIRLO® clad fuel rods were shipped to Oak Ridge National Laboratory (ORNL). The Sister Rods project is supporting US Department of Energy (DOE)'s “High Burnup Spent Fuel Data Project”, focusing on “understanding the effects of long-term storage and transportation on high burnup (HBU) (>45 GWD/MTU) light water reactor fuel”. The ZIRLO rods from the Sister Rods program are representative of a majority of Westinghouse's used fuel with ZIRLO cladding with rod-average burnup ranging from 48 to 59 GWd/MTU and a standard 9.5 mm (0.374 inches) rod diameter in a 17×17 array. Some performance characteristics of the entire ZIRLO sister rods are being obtained at ORNL, including visual, axial growth and in-reactor corrosion. The rod internal pressure and fission gas release were obtained from both ORNL and PNNL (Pacific Northwest National Laboratory). The characteristics and performance of ZIRLO sister rods are being evaluated for transportation and interim/long term storage. The evaluation includes comparing the measurement data with historical databases as well as model predictions. This paper will report the evaluations of the characteristics and performance of ZIRLO sister rods for transportation and storage.

KW - Characteristics

KW - Dry storage

KW - High burnup

KW - Performance

KW - Sister rods

KW - Used nuclear fuel

KW - ZIRLO cladding

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M3 - Paper

AN - SCOPUS:85081085209

SP - 77

EP - 84

T2 - 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019

Y2 - 22 September 2019 through 27 September 2019

ER -

Characteristics and performance of zirlo cladding used fuel

Abstract

Conference

Funding

Keywords

UN SDGs

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