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Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel

Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel

Author(s)
Broadhead, B. L. ,
DeHart, M. D. ,
Ryman, J. C. ,
Tang, J. S. ,
Parks, C. V.
Publication Date
The radionuclide characteristics of light-water-reactor (LWR) spent fuel play key roles in the design and licensing activities for radioactive waste transportation systems, interim storage facilities, and the final repository site.
burnup credit spent fuel transport lwr ornl/tm-12742 nuclide used fuel

Validation of SCALE-4 for Burnup Credit Applications

Validation of SCALE-4 for Burnup Credit Applications

Author(s)
Bowman, S. M. ,
DeHart, M. D. ,
Parks, C. V.
Publication Date

In the past, criticality analysis of pressurized water reactor (PWR) fuel stored in racks and casks has assumed that the fuel is fresh with the maximum allowable initial enrichment. If credit is allowed for fuel burnup in the design of casks that are used in the transport of spent light water reactor fuel to a repository, the increase in payload can lead to a significant reduction in the cost of transport and a potential reduction in the risk to the public. A portion of the work has been performed at Oak Ridge National Laboratory (ORNL) in support of the U.S.

burnup credit criticality pwr transport code nuclear reactor nuclear fuel irradiated nuclear fuel

Research to Support Expansion of U.S. Regulatory Position on Burnup Credit for Transport and Storage Casks

Research to Support Expansion of U.S. Regulatory Position on Burnup Credit for Transport and Storage Casks

Author(s)
Parks, C. V. ,
Wagner, J. C. ,
Gauld, I. C.
Publication Date

In 1999, the United States Nuclear Regulatory Commission (U.S. NRC) initiated a research program
to support the development of technical bases and guidance that would facilitate the implementation of burnup
credit into licensing activities for transport and dry cask storage. This paper reviews the following major areas of
investigation: (1) specification of axial burnup profiles, (2) assumption on cooling time, (3) allowance for
assemblies with fixed and removable neutron absorbers, (4) the need for a burnup margin for fuel with initial

burnup credit dry cask storage transport axial burnup profile

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report from Norway, Fourth Review Meeting, 14-23 May 2012

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report from Norway, Fourth Review Meeting, 14-23 May 2012

Author
Norwegian Radiation Protection Authority
Publication Date

This is the Norwegian report to the fourth review meeting to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (Joint Convention) to be held at IAEA in Vienna, 14–23 May 2012. Norway signed the Joint Convention on 29 September 1997, the day it was opened for signature. The Joint Convention was ratified and deposited on 12 January 1998.

siting national report joint convention spent fuel management norway radioactive waste management
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