Resources
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Type:PATRAM Proceedings
Abstract:
A recent structural analysis of the T-3 Spent Fuel Containment Cask found problems with the design of the attachment system. Assumptions in…
Type:PATRAM Proceedings
Abstract:
We will summarize a multinational, multi-phase spent fuel sabotage test program that quantifies aerosol particles produced when the…
Type:PATRAM Proceedings
Abstract:
During the last year, SOGIN (the Italian company in charge for decommissioning of Italian NPPs) had to predispose an accelerated…
Type:Annual Meeting Proceedings
Abstract:
The Strategic Arms Reduction Treaty (START I), a seminal arms control agreement that substantially reduced the levels of deployed strategic…
Type:PATRAM Proceedings
Abstract:
In 2002 an amendment of the German Atomic Energy Act fixed – beside a limitation of a certain amount of electricity generation – the stop…
Type:PATRAM Proceedings
Abstract:
The Federal Institute for Materials Research and Testing (BAM) is one of the two German competent authorities responsible for the Safety…
Type:PATRAM Proceedings
Abstract:
Advanced codes and guidelines for the assessment of component safety include fracture mechanics concepts in many cases. Regarding this,…
Type:PATRAM Proceedings
Abstract:
Even though there are provisions in NRC guidance for partial burnup credit, spent fuel assemblies have typically been analyzed for…
Type:PATRAM Proceedings
Abstract:
The United States Nuclear Regulatory Commission staff has proposed a study to demonstrate the robustness of spent nuclear fuel (SNF)…
Type:PATRAM Proceedings
Abstract:
This paper overviews current regulatory practices for the assurance of nuclear and radiation safety during railway transportation of SNF on…
Type:Annual Meeting Proceedings
Abstract:
A tamper indicating device (TID), used in conjunction with appropriate procedures for control, accounting and surveillance, is a tool used…
Type:PATRAM Proceedings
Abstract:
Modern finite element codes used in the design of nuclear material transportation and storage casks can readily calculate the response of…
Type:PATRAM Proceedings
Abstract:
Higher capacity baskets for storage and transport ofspent fuel provide an advantage ofALARA during loading operations and optimal use of…
Type:PATRAM Proceedings
Abstract:
Transport and storage cask for spent fuels is used for transport and storage of spent fuels. Integrity of containment system and…
Type:PATRAM Proceedings
Abstract:
Japan Nuclear Energy Safety Organization (JNES) will perform a welding inspection of dry cask for the spent fuel which will be one of…
Type:Annual Meeting Proceedings
Abstract:
We review several often overlooked sources of potential bias when assaying waste containers by gamma-ray spectrometry. These effects are…
Type:Annual Meeting Proceedings
Abstract:
The U.S./Russian Material Protection, Control, and Accounting (MPC&A) program has been active since 1994. In 1997, Oak Ridge National…
Type:PATRAM Proceedings
Abstract:
In this paper the IAEA regulatory 1m puncture bar drop test is considered from the viewpoint of using reduced-scale model packages. The…
Type:Annual Meeting Proceedings
Abstract:
The BWX Technologies (BWXT) Downblending Facility converted approximately 50 metric tonnes (MT) of highly enriched uranium (HEU) into…
Type:Annual Meeting Proceedings
Abstract:
Scheinman began his discussion by referencing the opening plenary conference speech by Paul Lisowski on the future on nuclear power and the…