scholarly journals Low enriched uranium fuel conversion and fuel shipping guide

1997 ◽  
Author(s):  
Keyword(s):  
Fuel Conversion ◽  
Uranium Fuel ◽  
Enriched Uranium

scholarly journals Low-Enriched Uranium Fuel Conversion Activities for the High Flux Isotope Reactor, Annual Report for FY 2011

2012 ◽  
Author(s):  
David G Renfro ◽  
David Howard Cook ◽  
James D Freels ◽  
Frederick P Griffin ◽  
Germina Ilas ◽  
...  
Keyword(s):  
Annual Report ◽  
High Flux ◽  
Fuel Conversion ◽  
Uranium Fuel ◽  
Enriched Uranium

scholarly journals Transitional cores and fuel cycle analyses in support of MIT reactor low enriched uranium fuel conversion

2020 ◽  
Vol 119 ◽  
pp. 103171 ◽  
Author(s):  
Kaichao Sun ◽  
Akshay J. Dave ◽  
Lin-wen Hu ◽  
Erik H. Wilson ◽  
Son Pham ◽  
...  
Keyword(s):  
Fuel Cycle ◽  
Fuel Conversion ◽  
Uranium Fuel ◽  
Enriched Uranium

scholarly journals AN APPLICATION OF IRIDM IN THE DECISION MAKING PROCESS ON FUEL CONVERSION OF THE MARIA REACTOR

2013 ◽  
Vol 3 (3) ◽  
pp. 3-6 ◽  
Author(s):  
Mieczysław Józef Borysiewicz ◽  
Karol Kowal ◽  
Piotr Andrzej Prusiński ◽  
Marcin Dąbrowski
Keyword(s):  
Decision Making ◽  
Research Reactor ◽  
Nuclear Research ◽  
Decision Making Process ◽  
Fuel Conversion ◽  
National Centre ◽  
Uranium Fuel ◽  
Integrated Risk ◽  
Enriched Uranium ◽  
Global Threat

Poland, when acceded to GTRI (Global Threat Reduction Initiative) in 2004, has committed to convert the nuclear fuel of the Research Reactor MARIA, operated by the National Centre for Nuclear Research (NCBJ) in Świerk. The conversion means giving up of high enriched uranium fuel containing 36% of U-235, which was used so far, and replacing it with the low enriched uranium fuel (19.7% U-235). This article describes the potential usability of the Integrated Risk Informed Decision Making (IRIDM) methodology in optimization of the fuel conversion procedure.

Preliminary Core Design and Optimization Analysis of Travelling Wave Reactor

2014 ◽  
Vol 1070-1072 ◽  
pp. 357-360
Author(s):  
Dao Xiang Shen ◽  
Yao Li Zhang ◽  
Qi Xun Guo
Keyword(s):  
Monte Carlo ◽  
Rational Design ◽  
Nuclear Reactor ◽  
Reactor Core ◽  
Travelling Wave ◽  
Optimization Analysis ◽  
Design And Optimization ◽  
Uranium Fuel ◽  
Enriched Uranium ◽  
Ignition Zone

A travelling wave reactor (TWR) is an advanced nuclear reactor which is capable of running for decades given only depleted uranium fuel, it is considered one of the most promising solutions for nonproliferation. A preliminary core design was proposed in this paper. The calculation was performed by Monte Carlo method. The burning mechanism of the reactor core design was studied. Optimization on the ignition zone was performed to reduce the amount of enriched uranium initially deployed. The results showed that the preliminary core design was feasible. The optimization analysis showed that the amount of enriched uranium could be reduced under rational design.

Lattice optimization for graphite moderated molten salt reactors using low-enriched uranium fuel

2017 ◽  
Vol 110 ◽  
pp. 1-10 ◽  
Author(s):  
Dallas Moser ◽  
Alexander Wheeler ◽  
Ondřej Chvála
Keyword(s):  
Molten Salt ◽  
Uranium Fuel ◽  
Enriched Uranium
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