Evaluation of Neutron Poison Materials for DOE SNF Disposal Systems

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Description

Aluminum-based spent nuclear fuel (Al-SNF) from foreign and domestic research reactors is being consolidated at the Savannah River Site (SRS) for ultimate disposal in the Mined Geologic Disposal System (MGDS). Most of the aluminum-based fuel material contains highly enriched uranium (HEU) (more than 20 percent 235U), which challenges the preclusion of criticality events for disposal periods exceeding 10,000 years. Recent criticality analyses have shown that the addition of neutron absorbing materials (poisons) is needed in waste packages containing DOE SNF canisters fully loaded with Al-SNF under flooded and degraded configurations to demonstrate compliance with the requirement that Keff less than ... continued below

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6 p.

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Vinson, D.W.; Caskey, G.R. Jr. & Sindelar, R.L. September 1, 1998.

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Description

Aluminum-based spent nuclear fuel (Al-SNF) from foreign and domestic research reactors is being consolidated at the Savannah River Site (SRS) for ultimate disposal in the Mined Geologic Disposal System (MGDS). Most of the aluminum-based fuel material contains highly enriched uranium (HEU) (more than 20 percent 235U), which challenges the preclusion of criticality events for disposal periods exceeding 10,000 years. Recent criticality analyses have shown that the addition of neutron absorbing materials (poisons) is needed in waste packages containing DOE SNF canisters fully loaded with Al-SNF under flooded and degraded configurations to demonstrate compliance with the requirement that Keff less than 0.95. Compatibility of poison matrix materials and the Al-SNF, including their relative degradation rate and solubility, are important to maintain criticality control. An assessment of the viability of poison and matrix materials has been conducted, and an experimental corrosion program has been initiated to provide data on degradation rates of poison and matrix materials and Al-SNF materials under repository relevant vapor and aqueous environments. Initial testing includes Al6061, Type 316L stainless steel, and A516Gr55 in synthesized J-13 water vapor at 50 degrees C, 100 degrees C, and 200 degrees C and in condensate water vapor at 100 degrees C. Preliminary results are presented herein.

Physical Description

6 p.

Notes

INIS; OSTI as DE98054567

Source

  • 3. American Nuclear Society (ANS) topical meeting on DOE spent nuclear fuel and fissile materials management, Charleston, SC (United States), 8-11 Sep 1998

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  • Other: DE98054567
  • Report No.: WSRC-MS--98-00450
  • Grant Number: AC09-96SR18500
  • Office of Scientific & Technical Information Report Number: 333860
  • Archival Resource Key: ark:/67531/metadc676162

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  • September 1, 1998

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  • July 25, 2015, 2:20 a.m.

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  • Feb. 10, 2016, 2:38 p.m.

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Vinson, D.W.; Caskey, G.R. Jr. & Sindelar, R.L. Evaluation of Neutron Poison Materials for DOE SNF Disposal Systems, article, September 1, 1998; Aiken, South Carolina. (digital.library.unt.edu/ark:/67531/metadc676162/: accessed September 24, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.