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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, Greek National Report

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Greek National Report

Author
GAEC
Publication Date

Greece has signed the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management on 5 September 1997. The Convention entered into force on 16 March 2000. The present report is the National Report of Greece for the Second Review Meeting to the Convention, which will take place 15-26 May 2006 at the IAEA in Vienna. The report has been prepared in accordance with the Guidelines regarding the Form and Structure of National Reports (IINFCIRC/604, 1 July 2002), established by the Contracting Parties under Article 29 of the Convention.

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