Resources

Items marked as restricted are available to members only. Join INMM today to access over 60 years of insight from experts in the nuclear materials management industry.

10B(n, α)7Li Reaction-Assisted Corrosion of Al-B4C Metal Matrix Composite Neutron Absorber Irradiated in Spent Nuclear Fuel Pool
Type:PATRAM Proceedings
Author(s):Jung Yunsong, Sangjoon Ahn, Kiyoung Kim
Abstract:
Al-B4C metal matrix composites (MMC) are neutron absorber materials widely used in spent fuel pool (SFP) to ensure the subcriticality with…
1648C Impact Validation And Verification
Type:PATRAM Proceedings
Author(s):Sean Perry
Abstract:
International Nuclear Services is the design authority for a nuclear transport package known as the 1648C. This package was to be re-…
30-year cooperation between US-Japan in area of nuclear nonproliferation and nuclear security
Type:Annual Meeting Proceedings
Author(s):Howard Menlove, Masato Hori, Yosuke Naoi, Hirofumi Tomikawa, Adrienne M. Lafleur, Naoko Noro, Michael Browne, Yoko Kawakubo, Kathryn Glynn, Brian Abeyta, Deborah Dale, Kevin Veal
Abstract:
30-year cooperation between US-Japan in area of nuclear nonproliferation and nuclear securityHirofumi Tomikawa1), Yoko Kawakubo1), Naoko…
3D Gamma-ray Mapping From An Unmanned Aerial System For International Nuclear Safeguards
Type:Annual Meeting Proceedings
Author(s):Kai Vetter, Ryan Pavlovsky, Tenzing Joshi
Abstract:
The Applied Nuclear Physics program at Lawrence Berkeley National Laboratory has developed a modular, gamma-ray mapping system, the…
5-Year Accelerated Corrosion Testing of MAXUS® for Spent Fuel Pool and Dry Cask Performance
Type:PATRAM Proceedings
Author(s):Matthew L. Eyre, Daisuke Nagasawa, Aaron C. Herfurth, Toshiaki Yamazaki
Abstract:
Many pool fuel storage racks and fuel storage/transportation packages incorporate neutron absorbers to improve the space efficiency of…
6 m3 Concrete Box Studies
Type:PATRAM Proceedings
Author(s):Conrad Izatt, Darryl Smith, Phillip Ashton
Abstract:
Magnox Ltd. is intending to use 6 m3 Concrete Boxes (CBs) for the packaging and disposal of Intermediate Level radioactive Waste (ILW) at a…
60th Annual Meeting - Opening Plenary Session
Type:JNMM
Volume:47
Issue:4
Author(s):Tammy Taylor, Therese Renis for Massimo Aparo
Abstract:
This article is a written recording of the Opening Plenary session at the INMM 60th Annual Meeting on Monday, July 15, 2019.
9981 Type AF Shipping Container Testing
Type:PATRAM Proceedings
Author(s):Fletcher M. Davis, Paul Blanton, Joshua Flach, Christopher Cable
Abstract:
The 9981 Type AF Shipping container was an adaptation from the 9979 Type AF container. It was designed to carry a heavier payload to meet…
A Bayesian Network Based Security Assessment Methodology for SMR Physical Protection Design
Type:Annual Meeting Proceedings
Author(s):Man-Sung Yim, Andhika Y. Prawira
Abstract:
Small and Modular Reactor (SMRs) have several features that will improve the safety and security of the plant. However, the decrease in…
A central limit approximation for dead time corrections in high rate measurements
Type:Annual Meeting Proceedings
Author(s):Chen Dubi, Rami Atar
Abstract:
Detector dead time, caused by both the physical attributes of the the detection process and the electronic registration system, is perhaps…
A Computational Fluid Dynamics Modeling Approach for the Design and Optimization of NUHOMS® MATRIX
Type:PATRAM Proceedings
Author(s):Hui Liu, Jane He, Venkata Venigalla
Abstract:
Due to the unavailability of nuclear fuel reprocessing and a permanent geologic repository in the United States, it has become increasingly…
A Distributed Ledger Technology (DLT) Approach to Monitoring UF6 Cylinders: Lessons Learned from TradeLens
Type:Annual Meeting Proceedings
Author(s):Paige Gasser
Abstract:
Every year thousands of tons of uranium hexafluoride (UF6) are produced and transported worldwide in international certified containers…
A new edition of the IAEA Transport Regulations : which consequences and lessons for the industry ?
Type:PATRAM Proceedings
Author(s):Pierre MALESYS
Abstract:
Transport of radioactive material has to comply with the national and international modal regulations for the transport of dangerous goods…
A new Type B(U) Fissile, flexible multi-size cask solution to your fuel transport requirements
Type:PATRAM Proceedings
Author(s):Christopher L. Dane, Paul Harding, Fabien LABERGRI, Mathias CHAZOT, Julien Patru, Constance Robeyns, Laurent Lievre
Abstract:
INS, as part of the NDA group, is in charge of the management of contracts between NDA & customers (reprocessing, waste return,…),…
A Nuclear Weapons Latency Computational Tool
Type:JNMM
Volume:47
Issue:3
Author(s):William S. Charlton
Abstract:
A novel nuclear weapons proliferation assessment method has been developed to determine a state’s nuclear weapons latency, the expected…
A Research Study to Perform a Risk Assessment of Truck/Trailer Transportation of Radioactive Material in Canada
Type:PATRAM Proceedings
Author(s):Jefrey Ramsay, Smain Yalaoui, Manorma Kumar, Caitlyn Cavanagh-Dollard, Rajesh Garg
Abstract:
There are over one million packages containing radioactive material being safely transported in Canada each year. Canadian regulations for…
A Review of U.S. DOE Activities to Manage, Package, Transport and Dispose of DOE Spent Nuclear Fuel
Type:PATRAM Proceedings
Author(s):Bret Leslie
Abstract:
The U.S. Nuclear Waste Technical Review Board (NWTRB) reviewed the U.S. Department of Energy’s (DOE) efforts to manage the inventory of…
A Review of “A Unified Theory of Measurement Errors and Uncertainties” in the Context of Uncertainty Quantification Used in Nuclear Safeguards
Type:Annual Meeting Proceedings
Author(s):Tom Burr, Brian Weaver, Andrea Favalli, Daniela Henzlova, Stephen Croft, Thomas Krieger
Abstract:
A Review of “A Unified Theory of Measurement Errors and Uncertainties” in the Context of Uncertainty Quantification Used in Nuclear…
A Study on Ageing of a Canister during Long-term Storage: Evaluation of the Influence of temperature difference between Canister Sureface and Environment on corrosion
Type:PATRAM Proceedings
Author(s):Masumi Wataru, Satoshi Hirohata, Daichi Sata
Abstract:
From the point of view of flexibility in the spent fuel management, it is important to provide options of dry storage technology. CRIEPI…
A Successful and Effective Transportation Program for the Shipment of Type A and Type B Quantities of Radioactive Material
Type:PATRAM Proceedings
Author(s):Greg Fulford
Abstract:
There are several requirements that make up a successful global transportation program for radioactive materials. This starts with a…