A source-term method for determining spent-fuel transport cask containment requirements: Executive summary

Technical Report · Mon Feb 01 00:00:00 EST 1993

DOI:https://doi.org/10.2172/6866921· OSTI ID:6866921

Sanders, T L; Seager, K D ^[1]; Reardon, P C ^[2]

---

1. Sandia National Labs., Albuquerque, NM (United States)
2. GRAM, Inc., Albuquerque, NM (United States)

This Executive Summary presents the methodology for determining containment requirements for spent-fuel transport casks under normal and hypothetical accident conditions. Three sources of radioactive material are considered: (1) the spent fuel itself, (2) radioactive material, referred to as CRUD, attached to the outside surfaces of fuel rod cladding, and (3) residual contamination adhering to interior surfaces of the cask cavity. The methodologies for determining the concentrations of freely suspended radioactive materials within a spent-fuel transport cask for these sources are discussed in much greater detail in three companion reports: A Method for Determining the Spent-Fuel Contribution to Transport Cask Containment Requirements,'' Estimate of CRUD Contribution to Shipping Cask Containment Requirements,'' and A Methodology for Estimating the Residual Contamination Contribution to the Source Term in a Spent-Fuel Transport Cask.'' Examples of cask containment requirements that combine the individually determined containment requirements for the three sources are provided, and conclusions from the three companion reports to this Executive Summary are presented.

• Research Organization: Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 6866921
• Report Number(s): SAND-90-2408; TTC-1021; ON: DE93011389
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
CONTAINERS
EVALUATION
SPENT FUELS
CONTAINMENT
CLADDING
CONCENTRATION RATIO
FUEL RODS
IMPACT SHOCK
LEAKS
PACKAGING
PACKAGING RULES
RADIOACTIVE WASTES
TRANSPORT
DEPOSITION
ENERGY SOURCES
FUEL ELEMENTS
FUELS
MATERIALS
NUCLEAR FUELS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTOR MATERIALS
REGULATIONS
SURFACE COATING
WASTES
050900* - Nuclear Fuels- Transport
Handling
& Storage
050800 - Nuclear Fuels- Spent Fuels Reprocessing
420204 - Engineering- Shipping Containers