Published 1994 | Version v1
Report Restricted

Simplified risk assessment for transporting ATR spent fuel within the INEL

Creators

  • 1. Argonne National Lab., Idaho Falls, ID (United States)
  • 2. Louisiana State Univ., Baton Rouge, LA (United States). Nuclear Science Center
  • 3. Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

Description

Interest in characterizing the condition of stored spent fuels has generated the need to move spent fuels to hot cell facilities within the Idaho National Engineering Laboratory (INEL). A simplified probabilistic risk assessment (SPRA) and an evaluation of the radiological consequences in the event of an accident are discussed and applied to on-site Advanced Test Reactor (AYR) spent fuel shipments. Reported accident probabilities between 10-4 and 10-6 and low radiological consequences, affords this, and other spent fuel characterization efforts, an additional option to move spent fuels within the INEL

Availability note (English)

MF available from INIS under the Report Number; Also available from OSTI as DE95009900; NTIS; US Govt. Printing Office Dep.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
9 p.
Report number
ANL--FO/CP-84381

Conference

Title
challenges and initiatives.
Acronym
Spent nuclear fuel meeting
Dates
14-16 Dec 1994.
Place
Salt Lake City, UT (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
26059787
Subject category
S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
ATR REACTOR; CHEMICAL ANALYSIS; IDAHO NATIONAL ENGINEERING LABORATORY; MATERIALS HANDLING; NUMERICAL DATA; POPULATION DENSITY; PROBABILISTIC ESTIMATION; RADIATION ACCIDENTS; RADIATION DOSES; RISK ASSESSMENT; ROAD TRANSPORT; SPENT FUEL CASKS; SPENT FUEL ELEMENTS; SPENT FUEL STORAGE
Descriptors DEC
ACCIDENTS; CASKS; CONTAINERS; DATA; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; INFORMATION; IRRADIATION REACTORS; LAND TRANSPORT; MATERIALS TESTING REACTORS; NATIONAL ORGANIZATIONS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; STORAGE; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; TRANSPORT; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Contract/Grant/Project number
Contract W-31109-ENG-38
Funding organization
USDOE, Washington, DC (United States).
Secondary number(s)
CONF-941207--36.