SURFACE FACILITY CRITICALITY SAFETY CALCULATIONS

Sanders, C.E.

United States. Department of Energy. Yucca Mountain Project Office.

关键词: Criticality;    Storage;    Pwr Type Reactors;    11 Nuclear Fuel Cycle And Fuel Materials;    Nuclear Fuels;   

DOI  :  10.2172/841257
RP-ID  :  100-00C-WHS0-00100-000-00B
RP-ID  :  NA
RP-ID  :  841257

美国|英语

来源: UNT Digital Library

【 摘 要 】

The purpose of this design calculation is to revise and update the previous criticality evaluation for the fuel handling, transfer and storage operations to be performed in the Surface Facility documented in BSC 2003c. The scope of this design calculation covers the operations in the Dry Transfer Facility (DTF) and Remediation Building (RB) and their processes as established at the date of this calculation. Also, this design calculation focuses on intact commercial spent nuclear fuel (SNF) assemblies, i.e., pressurized water reactor (PWR) and boiling water reactor (BWR) SNF. A description of the changes is as follows: (1) Update the supporting calculations for the various Category 1 and 2 event sequences as identified in the ''Preliminary Categorization of Event Sequences for License Application'' (BSC 2003a, Section 7). (2) Include comments from an informal review conducted by Y-12, located in Oak Ridge, Tennessee (Su 2004). (3) Revise the BWR calculations to reflect a different Boral loading. (4) Assess effects of potential moderator intrusion into the storage rack area with various water levels for defense in depth based on the new design of the DTF and RB.