Probabilistic safety analysis of transportation of spent fuel
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Probabilistic safety analysis of transportation of spent fuel

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Published by Bhabha Atomic Research Centre in Mumbai, India .
Written in English

Subjects:

Places:

  • India.

Subjects:

  • Spent reactor fuels -- India.

Book details:

About the Edition

With reference to India.

Edition Notes

Statementby Chitra Subramaniam.
SeriesBARC external ;, BARC/1999/E/036
ContributionsBhabha Atomic Research Centre., India.
Classifications
LC ClassificationsMicrofiche 2000/60396 (T)
The Physical Object
FormatMicroform
Paginationii, 167 p.
Number of Pages167
ID Numbers
Open LibraryOL6816442M
LC Control Number00288675

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Spent fuel storage and transportation comprises one of three sub-arenas that the staff of the U.S. Nuclear Regulatory Commission (NRC) identified in considering which areas of the waste management arena to target for greater use of risk information. @article{osti_, title = {Spent fuel transportation on highways: the radioactive dose to the traffic}, author = {Yadigaroglu, G.}, abstractNote = {The radioactive exposure of the traffic moving on the same highway as spent fuel shipments has been neglected in the past. Methods developed for calculating peak exposures, the number of individuals receiving a dose in . This paper proposes a methodology to assess and reduce risks of maritime spent nuclear fuel transportation with a probabilistic approach. Event trees detailing the progression of collisions leading to transport casks’ damage were constructed. Parallel and crossing collision probabilities were formulated based on the Poisson by: The health and safety risks to be discussed in this chapter arise from exposures of people who travel, work, or live near transportation routes, and transportation workers themselves, to radiation (Sidebar ) from loaded spent fuel and high-level waste transportation packages. During normal operations, such exposures can occur as the result.

– Reexamination of Spent Shipment Risk Estimates (NUREG/CR, ) • NRC’s safety mission – Considering public comment, provide updated basis for NRC’s safety regulations applicable to spent fuel transportation • Outreach responsibilities – Reassure public regarding spent fuel shipments. Probabilistic Safety Analysis Lecture Prof. Andrew C. Kadak, Department of Nuclear Science & Engineering Page 2 Topics to be Covered • Probabilistic Basics † Cool the Reactor and Spent Fuel Maintain coolant inventory Maintain coolant flow Maintain coolant heat sinks KEEP RADIOACTIVE MATERIAL OUT OF THE BIOSPHERE.   Starting when the uranium is taken from the ground, the NRC oversees its processing and manufacture into fuel to be used in reactors. The NRC also plays a role in ensuring the safe transportation, storage, and permanent geologic disposal of used fuel. The NRC works to protect public health and safety, the environment, and our national security. the work begun by NFST, to develop an integrated waste management system for spent nuclear fuel (SNF), including the development of a large-scale transportation system for the safe transport of SNF to storage or disposal facilities.

v REPORT SUMMARY This report presents a probabilistic treatment of longitudinal tearing of spent fuel rods subjected to dynamic forces that could result from hypothetical spent fuel transportation accidents. Probabilistic Safety Analysis (PSA) is a method of fault analysis focussed on ensuring that a nuclear facility, plant or site is adequately safe against a wide range of faults and hazards. It is complementary to other methods of fault analysis such as Design Basis Analysis (DBA) and Severe Accident Analysis (SAA). Probabilistic Safety Analysis Document Type: Nuclear Safety Technical Assessment Guide Unique Document ID and Revision No: NS-TAST-GD Revision 6 Date Issued: June Review Date: June Approved by: R Moscrop Professional Lead Fault Analysis Record Reference: CM9 /File Size: KB. Probabilistic Safety Assessment. evaluated the probability of a number of accident sequences that might lead to melting of the fuel in the reactor the analysis is still considered to be conservative since credit is not taken for all plant equipment or human actions that could mitigate accidents considered.