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Einziger RE, Cook JA. Behavior of Breached Light Water Reactor Spent Fuel Rods in Air and Inert Atmospheres at 229°C. NUCL TECHNOL 2017. [DOI: 10.13182/nt85-a33595] [Citation(s) in RCA: 18] [Impact Index Per Article: 2.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Robert E. Einziger
- Westinghouse Hanford Company, Mail Stop W/A-40 P.O. Box 1970, Richland, Washington 99352
| | - James A. Cook
- EG&G Idaho, Inc., P.O. Box 1625, Idaho Falls, Idaho 83415
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2
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Mayuzumi M, Onchi T. A Method to Evaluate the Maximum Allowable Temperature of Spent Fuel in Dry Storage During a Postulated Accident. NUCL TECHNOL 2017. [DOI: 10.13182/nt91-a34532] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Masami Mayuzumi
- Central Research Institute of Electric Power Industry 2-11-1 Iwato-kita, Komae-shi, Tokyo 210, Japan
| | - Takeo Onchi
- Central Research Institute of Electric Power Industry 2-11-1 Iwato-kita, Komae-shi, Tokyo 210, Japan
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Porsch G, Fleisch J, Heits B. Accelerated High-Temperature Tests with Spent PWR and BWR Fuel Rods Under Dry Storage Conditions. NUCL TECHNOL 2017. [DOI: 10.13182/nt86-a33831] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Gerd Porsch
- NUKEM GmbH, P.O. Box 110080 D 6450 Hanau 11, Federal Republic of Germany
| | - Joachim Fleisch
- Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, P.O. Box 1407, D 3000 Hannover 1, Federal Republic of Germany
| | - Bernd Heits
- Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, P.O. Box 1407, D 3000 Hannover 1, Federal Republic of Germany
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Kohli R, Stahl D, Pasupathi V, Johnson AB, Gilbert ER. The Behavior of Breached Boiling Water Reactor Fuel Rods on Long-Term Exposure to Air and Argon at 598 K. NUCL TECHNOL 2017. [DOI: 10.13182/nt85-a33630] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- R. Kohli
- Battelle Columbus Laboratories, Columbus, Ohio 43201-2693
| | - D. Stahl
- Battelle Columbus Laboratories, Columbus, Ohio 43201-2693
| | - V. Pasupathi
- Battelle Columbus Laboratories, Columbus, Ohio 43201-2693
| | - A. B. Johnson
- Battelle Pacific Northwest Laboratories, Richland, Washington 99352
| | - E. R. Gilbert
- Battelle Pacific Northwest Laboratories, Richland, Washington 99352
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5
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Einziger RE, Kohli R. Low-Temperature Rupture Behavior of Zircaloy-Clad Pressurized Water Reactor Spent Fuel Rods Under Dry Storage Conditions. NUCL TECHNOL 2017. [DOI: 10.13182/nt84-a33534] [Citation(s) in RCA: 20] [Impact Index Per Article: 2.9] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Robert E. Einziger
- Westinghouse Hanford Company, P.O. Box 1970 Mail Stop W/A-40, Richland, Washington 99352
| | - Rajiv Kohli
- Battelle Columbus Laboratories, 505 King Avenue Columbus, O/i/o 45207
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Creep assessment of Zry-4 cladded high burnup fuel under dry storage. PROGRESS IN NUCLEAR ENERGY 2011. [DOI: 10.1016/j.pnucene.2011.01.012] [Citation(s) in RCA: 11] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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A fracture mechanics-based model for assessing the mechanical failure of nuclear fuel rods due to rock fall. NUCLEAR ENGINEERING AND DESIGN 2000. [DOI: 10.1016/s0029-5493(00)00270-3] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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8
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MAYUZUMI M, ONCHI T, MATSUO Y. Failure Propensities of Pressurized Zircaloy Tube Containing Iodine and Other Chemical Species. J NUCL SCI TECHNOL 1993. [DOI: 10.1080/18811248.1993.9734624] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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