Fracture mechanics based design for radioactive material transport packagings -- Historical review

1998 ◽  
Author(s):  
J.A. Smith ◽  
D. Salzbrenner ◽  
K. Sorenson ◽  
P. McConnell
Keyword(s):  
Fracture Mechanics ◽  
Historical Review ◽  
Radioactive Material ◽  
Material Transport

Field Experience With Code Case N-659: Ultrasonic Examination in Lieu of Radiography

2007 ◽  
Author(s):  
Douglas O. Henry
Keyword(s):  
Nuclear Power ◽  
Cost Benefit ◽  
Nuclear Regulatory Commission ◽  
Radioactive Material ◽  
Material Transport ◽  
Ultrasonic Examination ◽  
Key Factor ◽  
Asme Code ◽  
Regulatory Commission ◽  
Sample Set

Code Case N-659 Revision 0 was approved in 2002 to allow ultrasonic examination (UT) an alternative to radiography (RT) for nuclear power plant components and transport containers under Section III of the ASME Code. The Nuclear Regulatory Commission has not approved N-659 and its subsequent revisions (currently N-659-2) for general use, but they have been used on a case-by-case basis mainly where logistic problems or component configuration have prevented the use of radiography. Like the parallel Code Case 2235 for non-nuclear applications under Section I and Section VIII, Code Case N-659 requires automated, computerized ultrasonic systems and capability demonstration on a flawed sample as a prerequisite for using UT in lieu of RT. Automated ultrasonic examination can be significantly more expensive than radiography, so a cost-benefit evaluation is a key factor in the decision to use the Code Case. In addition, the flaw sample set has recently become an issue and a topic of negotiation with the NRC for application of the Case. A flaw sample set for a recent radioactive material transport cask fabrication project was successfully negotiated with the NRC. The Code Case N-659 approach has been used effectively to overcome barriers to Code required radiography. Examples are examination of welds in an assembled heat exchanger and in a radioactive material transport cask assembly where internal shielding prevented radiography of the weld. Future development of Code Case N-659 will address sample set considerations and application-specific Code Cases, such as for storage and transport containers, will be developed where NRC concerns have been fully addressed and regulatory approval can be obtained on a generic basis.

Security in the Transport of Radioactive Materials

2009 ◽  
Author(s):  
Ronald B. Pope ◽  
Richard R. Rawl
Keyword(s):  
The United States ◽  
Department Of Energy ◽  
Radioactive Material ◽  
United States Department ◽  
Guidance Document ◽  
Material Transport ◽  
Radioactive Materials ◽  
Energy Agency ◽  
Donor States ◽  
Global Threat

The United States Department of Energy National Nuclear Security Administration’s (DOE/NNSA) Global Threat Reduction Initiative (GTRI), the International Atomic Energy Agency (IAEA) and active IAEA Donor States are working together to strengthen the security of nuclear and radioactive materials during transport to mitigate the risks of theft, diversion, or sabotage. International activities have included preparing and publishing the new IAEA guidance document Security in the Transport of Radioactive Material while ensuring that security recommendations do not conflict with requirements for safety during transport, and developing and providing training programs to assist other countries in implementing radioactive material transport security programs. This paper provides a brief update on the status of these transportation security efforts.

Experiences on Radioactive Materials Safe Transport in CIRP

2018 ◽  
Author(s):  
Zhang Jiangang ◽  
Li Guoqiang ◽  
Wang Renze ◽  
Sun Hongchao ◽  
Zhuang Dajie ◽  
...  
Keyword(s):  
Water Immersion ◽  
Immersion Test ◽  
Assessment Method ◽  
Radioactive Material ◽  
Test Scheme ◽  
Measurement Means ◽  
Material Transport ◽  
Safe Transport ◽  
Normal Transport ◽  
Accident Conditions

The safety of radioactive material transport is regulated by graded approach in China. National requirements on container design, manufacture and shipment are different for the three categories material. Packages of different categories shall be experienced different test to demonstrate their ability to withstand transport normal transport conditions and accident conditions depending on their contents. China Institute for Radiation Protection (CIRP) established free drop test facilities, thermal test facilities, water immersion test facilities and relevant measurement means. CIRP has carried out tests of 18 radioactive material transport packages, and accumulate a lot of experiences about the limit unit analysis, test scheme, test process, monitoring and data treatment. Probabilistic safety assessment method and traffic accident statistics in China are carried out in the recent years by CIRP.

Research and Development of CRAMTRA 1.0 Code for Consequence Assessment From Radioactive Material Transport

2017 ◽  
Author(s):  
Wang Renze ◽  
Zhang Jiangang ◽  
Li Guoqiang ◽  
Zhuang Dajie ◽  
Sun Hongchao ◽  
...  
Keyword(s):  
Intellectual Property ◽  
Property Rights ◽  
Research And Development ◽  
Intellectual Property Rights ◽  
Radioactive Material ◽  
Material Transport ◽  
Western Countries ◽  
Consequence Assessment

Code for consequence assessment (CA) from radioactive material transport (RMT) is an important tool for RMT CA. Since 1980s relevant codes have been introduced from western countries to China, however, there isn’t a code with independent intellectual property rights of China. Design, programming and test of CRAMTRA 1.0 code for RMT CA was introduced in this paper, the results show that CRAMTRA 1.0 has reliable quality and fine practicability.

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