scholarly journals Dehydrogenation of ammonia-borane by cationic Pd(ii) and Ni(ii) complexes in a nitromethane medium: hydrogen release and spent fuel characterization

2015 ◽  
Vol 44 (16) ◽  
pp. 7373-7381 ◽  
Author(s):  
Sung-Kwan Kim ◽  
Sung-Ahn Hong ◽  
Ho-Jin Son ◽  
Won-Sik Han ◽  
Artur Michalak ◽  
...  
Keyword(s):  
Experimental Study ◽  
Ammonia Borane ◽  
Hydrogen Release ◽  
Spent Fuel ◽  
Fuel Characterization

This work provides a comprehensive experimental study on the mechanism of AB dehydrogenation with the [Pd(MeCN)4][BF4]2 (1) catalyst.

Promoted hydrogen release from ammonia borane with mannitolvia a solid-state reaction route

2012 ◽  
Vol 41 (3) ◽  
pp. 871-875 ◽  
Author(s):  
Yuede Pan ◽  
Yan Wang ◽  
Yanliang Liang ◽  
Zhanliang Tao ◽  
Jun Chen
Keyword(s):  
Solid State ◽  
Solid State Reaction ◽  
Ammonia Borane ◽  
Hydrogen Release ◽  
Reaction Route ◽  
Solid State Reaction Route

scholarly journals Experimental study on elemental behaviors in fluorination of nuclear spent fuel with flame reactor

2015 ◽  
Vol 53 (4) ◽  
pp. 513-520
Author(s):  
Daisuke Watanabe ◽  
Yuko Kani ◽  
Akira Sasahira ◽  
Kuniyoshi Hoshino ◽  
Fumio Kawamura
Keyword(s):  
Experimental Study ◽  
Spent Fuel ◽  
Flame Reactor

scholarly journals Strengthening the SSTC NRS Scientific and Technical Potential through Participation in the IAEA Coordinated Research Projects

2021 ◽  
pp. 5-13
Author(s):  
Yu. Balashevska ◽  
D. Gumenyuk ◽  
Iu. Ovdiienko ◽  
O. Pecherytsia ◽  
I. Shevchenko ◽  
...  
Keyword(s):  
Best Practices ◽  
Safety Assessment ◽  
Radiation Safety ◽  
Research Projects ◽  
Spent Fuel ◽  
Research Activities ◽  
Technical Potential ◽  
Technical Issues ◽  
Fuel Characterization ◽  
Definition Of

The State Scientific and Technical Center for Nuclear and Radiation Safety (SSTC NRS), a Ukrainian enterprise with a 29-year experience in the area of scientific and technical support to the national nuclear regulator (SNRIU), has been actively involved in international research activities. Participation in the IAEA coordinated research activities is among the SSTC NRS priorities. In the period of 2018–2020, the IAEA accepted four SSTC NRS proposals for participation in respective Coordinated Research Projects (CRPs). These CRPs address scientific and technical issues in different areas such as: 1) performance of probabilistic safety assessment for multi-unit/multi-reactor sites; 2) use of dose projection tools to ensure preparedness and response to nuclear and radiological emergencies; 3) phenomena related to in-vessel melt retention; 4) spent fuel characterization. This article presents a brief overview of the abovementioned projects with definition of scientific contributions by the SSTC NRS (participation in benchmarks, development of methodological documents on implementing research stages and of IAEA technical documents (TECDOC) for demonstration of best practices and results of research carried out by international teams).

scholarly journals Nano-inclusion in one step: spontaneous ice-templating of porous hierarchical nanocomposites for selective hydrogen release

2019 ◽  
Vol 3 (2) ◽  
pp. 396-400 ◽  
Author(s):  
Simon Champet ◽  
Jan van den Berg ◽  
Robert Szczesny ◽  
Agata Godula-Jopek ◽  
Duncan H. Gregory
Keyword(s):  
Graphene Oxide ◽  
Reduced Graphene Oxide ◽  
Ammonia Borane ◽  
Onset Temperature ◽  
Hydrogen Release ◽  
Aqueous Suspensions ◽  
Reduced Graphene ◽  
One Step ◽  
Ice Templating

3-D nanocomposites of (reduced) graphene oxide and ammonia borane can be fabricated in a one-step ice templating process from aqueous suspensions. The nanocomposites release hydrogen at a reduced onset temperature, suppressing the release of diborane, borazine and ammonia.

scholarly journals Experimental Study of Factors Affecting Hypergolic Ignition of Ammonia Borane

2020 ◽  
pp. 1-9
Author(s):  
Kathryn A. Clements ◽  
Michael J. Baier ◽  
P. Veeraraghavan Ramachandran ◽  
Steven F. Son
Keyword(s):  
Experimental Study ◽  
Ammonia Borane ◽  
Factors Affecting

Applications of Nuclear Data Covariances to Criticality Safety and Spent Fuel Characterization

2014 ◽  
Vol 118 ◽  
pp. 341-345 ◽  
Author(s):  
M.L. Williams ◽  
G. Ilas ◽  
W.J. Marshall ◽  
B.T. Rearden
Keyword(s):  
Nuclear Data ◽  
Spent Fuel ◽  
Fuel Characterization ◽  
Criticality Safety

Strength and Toughness of Steel Fiber Reinforced Heavy Concrete

2012 ◽  
Vol 512-515 ◽  
pp. 2908-2913 ◽  
Author(s):  
Yu Cheng Kan ◽  
Hsuan Chih Yang ◽  
Kuang Chih Pei
Keyword(s):  
Experimental Study ◽  
Compressive Strength ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Iron Ore ◽  
Steel Fiber ◽  
Test Results ◽  
Spent Fuel ◽  
Normal Concrete

This paper presents an experimental study dealing with the toughness of heavy concrete based on the ASTM C1018. Mixtures including 0%, 0.5%, 1.0% and 1.5% of steel fiber content by volume are designated, which are developed based on a mixture used in Kuosheng nuclear power plant in Taiwan. Metallic aggregates of iron shots and iron ore take 48.8% by volume in that mixture. Test results reveal that the compressive strength and rupture modulus of heavy concrete turn out higher than those of normal concrete. In addition, flexural toughness of heavy concrete grow with the steel fiber fraction, which is valid and appropriate for construction of shielding structure and spent fuel cask.

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