Resources

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DEVELOPMENT OF A NEW TRANSPORTATION/STORAGE CASK SYSTEM FOR USE BY THE DOE RUSSIAN RESEARCH REACTOR FUEL RETURN PROGRAM
Type:PATRAM Proceedings
Author(s):Michael Tyacke, Frantisek Svitak, Jiri Rychecky, Miroslav Picek, Alexey Smirnov, Surgey Komarov, E. Bradley, Alexander Dudchenko, Konstantin Golubkin
Abstract:
The United States, the Russian Federation, and the International Atomic Energy Agency (IAEA) have been working together on a program called…
Development of a Non-Metallic Composite Fuel Support Structure For Transport And Storage
Type:PATRAM Proceedings
Author(s):Charles J. Temus, Alec Ross
Abstract:
A new package for the transport and storage of CANDU® reactor fuel includes the use of stackable fuel bundle support trays made from…
Development of a Type B PWR Fresh Fuel Package
Type:PATRAM Proceedings
Author(s):Charles J. Temus, R. Montgomery
Abstract:
A Type B fresh fuel package has been developed to ship two PWR fuel assemblies. The package maximizes the number of fuel assemblies that…
Development of a World Institute of Nuclear Security
Type:Annual Meeting Proceedings
Author(s):James W. Tape
Abstract:
Tape discussed ‘Developing the Concept for a World Institute of Nuclear Security (WINS), Progress and Prospects on the Promulgation of…
DEVELOPMENT OF BORATED ALUMINUM MATERIAL FOR BASKET OF TRANSPORT/STORAGE CASKS
Type:PATRAM Proceedings
Author(s):Jun Shimojo, Hiroshi Akamatsu, Hiroaki Taniuchi, Da YOKOE
Abstract:
Enriched borated aluminum alloys suitable for application to baskets in transport and storage casks for high burn-up spent fuels have been…
DEVELOPMENT OF CONTENTS SPECIFICATIONS FOR THE TRANSPORT OF RADIOACTIVE WASTE
Type:PATRAM Proceedings
Author(s):Iain Gray, Bill Sievwright
Abstract:
As part of the process in the UK to assess the suitability of proposals for the packaging of intermediate level radioactive waste (ILW) for…
Development of cross section SFCX-J33 for spent fuel transport cask shielding calculation
Type:PATRAM Proceedings
Author(s):M. Matsumoto, Naoteru Odano, Seiki OHNISHI, Makoto Morishima, M. Ohmura
Abstract:
The transport cask shielding analysis in Japan is carried out using the 2-dimensional Sn transport calculation code DOT2) and cross section…
Development of Enterprise-Wide MPC&A Sustainability Programs at Two Facilities in the Russian Federation
Type:Annual Meeting Proceedings
Author(s):Michael Carroll, Richard Dowe Dabbs, Esther Ku, Dr. Thomas J. Abraham
Abstract:
The sustainability of upgrades completed under the United States Department of Energy (DOE) Material Protection, Control and Accounting (…
Development of External Fin Structure for Transport and Storage Cask and Verification of Its Heat Dissipation Performance
Type:PATRAM Proceedings
Author(s):Daiichi Ishiko, Takeshi Ichihashi, Kouichi Tanimoto, Hironori Noguchi
Abstract:
To improve heat dissipation performance for the transport and storage cask, applicability of short and compact external fins (micro fins)…
DEVELOPMENT OF FORGED STEEL APPLIED TO MAIN BODY OF TYPE B(U) PACKAGE
Type:PATRAM Proceedings
Author(s):Toshihiro Matsuoka, Kiminobu HOJO, Kentaro Yoshimoto, Ryuichi Yamamoto
Abstract:
Mitsubishi Heavy Industries, Ltd. (MHI) has developed MSF-57BG spent fuel transport and storage cask. Newly developed forged steel is…
Development of FT-II Code for Dynamic Analysis of Thermal Energy Transfer Caused by Fission Fragments
Type:Annual Meeting Proceedings
Author(s):T. Okamoto, Y. Ono
Abstract:
Fission track method for strengthening the safeguards system is expected to be very useful to detect undeclared nuclear activities. An…
DEVELOPMENT OF KATS - ECO-FRIENDLY SPENT FUEL TRANSPORT AND STORAGE CASK
Type:PATRAM Proceedings
Author(s):H. Taniuchi, S. Nakasuku, H. Akamatsu, Jun Shimojo
Abstract:
A new type of Eco-friendly Spent Fuel Transport and Storage Cask named KATS has heen developed, of which the main gamma shielding is…
DEVELOPMENT OF NEUTRON ABSORBER (MAXUSTM) FOR HIGH BURN-UP SPENT NUCLEAR FUEL
Type:PATRAM Proceedings
Author(s):Toshiaki YAMAZAKI, Kazuto Sanada, Toshimasa Nishiyama, Hideki Ishii
Abstract:
B-AL (Boron-Aluminium) plate is commonly used as a neutron absorption material for the basket plate of casks. For material property reasons…
DEVELOPMENT OF NEW MONITORING SYSTEM FOR ACTIVITY DISTRIBUTION ESTIMATION IN LARGE WASTE CONTAINER FOR LSA-II MATERIAL
Type:PATRAM Proceedings
Author(s):Michiya Sasaki, Takatoshi Hattori
Abstract:
Low-level radioactive waste generated from the operation of nuclear power plants is currently being stored in 200-L metal drums and…
Development of Next Generation Advanced Remote Monitoring System
Type:Annual Meeting Proceedings
Author(s):Dennis Nelson, Rustem Samigulin, Sergey Blagin, Alexey Veselov, Andrey Kokoulin
Abstract:
The paper describes the latest upgrades for the Advanced Remote Monitoring System (ARMS) designed for monitoring access to a fissile…
Development of Rail Transport Solution to Support Transport of Large Nuclear Packages on Restricted Rail Routes
Type:PATRAM Proceedings
Author(s):Callum Mclaurin
Abstract:
For many years BNFL (now Sellafield Ltd) has transported spent nuclear fuel to Sellafield via Barrow using specially designed rail vehicles…
Development of the Nonproliferation Assessment Tool (NAT) Software Package for the Calculation of Proliferation Resistance Values of Nuclear Fuel Cycle Facilities
Type:JNMM
Volume:35
Issue:2
Author(s):Victoria Pratt, Kendra Foltz Biegalski, Sheldon Landsberger
Abstract:
Quantitative assessment methodologies have been developed and applied to evaluating the proliferation resistance (PR) of nuclear fuel…
Development of the Special Form Capsule for Sealed Sources
Type:JNMM
Volume:35
Issue:3
Author(s):Cristy L. Abeyta, Danny A. Martinez
Abstract:
The Off-Site Source Recovery Project (OSRP) at the Los Alamos National Laboratory (LANL) recovers and manages excess and unwanted…
DEVELOPMENT OF THE URANYL NITRATE CALIBRATION LOOP EQUIPMENT (UNCLE) AT ORNL
Type:Annual Meeting Proceedings
Author(s):Jennifer L. Ladd-Lively
Abstract:
The successful completion of a field trial of safeguards monitoring equipment at a natural uranium conversion plant (NUCP) demonstrated the…
DEVELOPMENT OF TYPE IP-2 PACKAGES FOR LOW AND INTERMEDIATE LEVEL RADIOACTIVE WASTE
Type:PATRAM Proceedings
Author(s):Sunghwan Chung, Kyu-Sup Choi, Minchul Kim, Seungho Lee
Abstract:
Korea Hydro and Nuclear Power Co., Ltd.(KHNP) is developing two kinds of IP-2 packages to transport low and intermediate radioactive waste(…