Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

Maheras, Steven J.¹  Best, Ralph E.¹  Ross, Steven B.¹  Buxton, Kenneth A.¹  England, Jeffery L.²  McConnell, Paul E.²  Massaro, Lawrence M.¹  Jensen, Philip J.¹ 

[1] Pacific Northwest National Lab. (PNNL), Richland, WA (United States);Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

关键词: LOW-LEVEL RADIOACTIVE WASTES;    SPENT FUELS;    REMOVAL;    REACTOR DECOMMISSIONING;    EVALUATION;    INFORMATION;    SPENT FUEL CASKS;    INVENTORIES;    PHOTOGRAPHY;    LAND TRANSPORT;    CONNECTICUT YANKEE REACTOR;    MAINE YANKEE REACTOR;    ROWE YANKEE REACTOR;    VERMONT YANKEE REACTOR;    HUMBOLDT BAY REACTOR;    BIG ROCK POINT REACTOR;    RANCHO SECO-1 REACTOR;    RANCHO SECO-2 REACTOR;    TROJAN REACTOR;    LACBWR REACTOR;    ZION-1 REACTOR;    ZION-2 REACTOR;    CRYSTAL RIVER-3 REACTOR;    CRYSTAL RIVER-4 REACTOR;    KEWAUNEE REACTOR;    SAN ONOFRE-1 REACTOR;    SAN ONOFRE-2 REACTOR;    SAN ONOFRE-3 REACTOR;    INFORMATION NEEDS;    DOCUMENTATION NFST;    shutdown sites;    used nuclear fuel;    spent nuclear fuel;   

DOI  :  10.2172/1255412
RP-ID  :  PNNL--22676 Rev. 6
PID  :  OSTI ID: 1255412
Others  :  Other: AF5865020
Others  :  TRN: US1601416

学科分类：核能源与工程

美国|英语

来源: SciTech Connect

【 摘 要 】

A preliminary evaluation of removing spent nuclear fuel (SNF) from 13 shutdown nuclear power reactor sites was conducted. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, San Onofre, and Vermont Yankee. The evaluation was divided into four components: (1) characterization of the SNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory, (2) a description of the on-site infrastructure and conditions relevant to transportation of SNF and GTCC waste, (3) an evaluation of the near-site transportation infrastructure and experience relevant to shipping transportation casks containing SNF and GTCC waste, including identification of gaps in information, and (4) an evaluation of the actions necessary to prepare for and remove SNF and GTCC waste. Every site was found to have at least one off-site transportation mode option for removing its SNF and GTCC waste; some have multiple options. Experience removing large components during reactor decommissioning provided an important source of information used to identify the transportation mode options for the sites. Especially important in conducting the evaluation were site visits, through which information was obtained that would not have been available otherwise. Extensive photographs taken during the site visits proved to be particularly useful in documenting the current conditions at or near the sites. It is expected that additional site visits will be conducted to add to the information presented in the evaluation.