scholarly journals Comparison Of A Neutron Kinetics Parameter For A Polyethylene Moderated Highly Enriched Uranium System

2017 ◽  
Author(s):  
George Espy McKenzie, IV ◽  
Joetta Marie Goda ◽  
Travis Justin Grove ◽  
Rene Gerardo Sanchez
Keyword(s):  
Neutron Kinetics ◽  
Enriched Uranium ◽  
Kinetics Parameter

Similarity theory in neutron kinetics and its implications for RFNC—VNIIEF applied research

2011 ◽  
Vol 181 (9) ◽  
pp. 953
Author(s):  
Nikolai B. Babichev ◽  
Pavel S. Bondarev ◽  
Vasilii P. Neznamov
Keyword(s):  
Applied Research ◽  
Similarity Theory ◽  
Neutron Kinetics

Development of the coupled 3D neutron kinetics/thermal-hydraulics code DYN3D-HTR for the simulation of transients in block-type HTGR

Kerntechnik ◽  
2011 ◽  
Vol 76 (3) ◽  
pp. 166-173
Author(s):  
U. Rohde ◽  
S. Baier ◽  
S. Duerigen ◽  
E. Fridman ◽  
S. Kliem ◽  
...  
Keyword(s):  
Block Type ◽  
Thermal Hydraulics ◽  
Neutron Kinetics

scholarly journals Separation of Lanthanide Isotopes from Mixed Fission Product Samples

Separations ◽  
2021 ◽  
Vol 8 (7) ◽  
pp. 104
Author(s):  
Leah M. Arrigo ◽  
Jun Jiang ◽  
Zachary S. Finch ◽  
James M. Bowen ◽  
Staci M. Herman ◽  
...  
Keyword(s):  
Fission Product ◽  
Fission Products ◽  
Nuclear Data ◽  
Product Analysis ◽  
Data Production ◽  
Thermal Irradiation ◽  
Nuclear Events ◽  
Lanthanide Separation ◽  
Enriched Uranium ◽  
Fission Yields

The measurement of radioactive fission products from nuclear events has important implications for nuclear data production, environmental monitoring, and nuclear forensics. In a previous paper, the authors reported the optimization of an intra-group lanthanide separation using LN extraction resin from Eichrom Technologies®, Inc. and a nitric acid gradient. In this work, the method was demonstrated for the separation and quantification of multiple short-lived fission product lanthanide isotopes from a fission product sample produced from the thermal irradiation of highly enriched uranium. The separations were performed in parallel in quadruplicate with reproducible results and high decontamination factors for 153Sm, 156Eu, and 161Tb. Based on the results obtained here, the fission yields for 144Ce, 153Sm, 156Eu, and 161Tb are consistent with published fission yields. This work demonstrates the effectiveness of the separations for the intended application of short-lived lanthanide fission product analysis requiring high decontamination factors.

Characterisation of Enriched Uranium Dioxide Particles from a Uranium Handling Facility

1998 ◽  
Vol 79 (1) ◽  
pp. 57-62 ◽  
Author(s):  
M.D. Hoover ◽  
G.J. Newton ◽  
R.A. Guilmette ◽  
R.J. Howard ◽  
R.N. Ortiz ◽  
...  
Keyword(s):  
Uranium Dioxide ◽  
Enriched Uranium

Construction of an Elementary Model for the Dynamic Analysis of a Pressurized Water Reactor

2013 ◽  
Vol 284-287 ◽  
pp. 652-656 ◽  
Author(s):  
Chiung Wen Tsai ◽  
Chun Kuan Shih ◽  
Jong Rong Wang
Keyword(s):  
Transfer Functions ◽  
Feedback Loops ◽  
Dynamic Responses ◽  
Coolant Temperature ◽  
Inlet Temperature ◽  
Pressurized Water Reactor ◽  
Elementary Model ◽  
Pressurized Water ◽  
Water Reactor ◽  
Neutron Kinetics

A lumped-parameter numerical model was constructed based on the conservation laws of mass and energy and the point neutron kinetics with 6 groups of delayed neutron to represent the dynamics of primary loop of a pressurized water reactor (PWR) core. On the viewpoint of control theory, the coupled phenomenon of neutron kinetics and thermohydraulics can be recognized as a dynamic system with feedback loops which is caused by the Doppler effect and the coolant temperature difference. Scilab was implemented to representing the equivalent transfer functions and associated feedback loops of a PWR core. The dynamic responses were performed by the perturbations of coolant inlet flow, coolant inlet temperature, and reactivity insertion.

Lie group analysis of the point-reactor neutron kinetics equations for various reactivity models

2021 ◽  
Vol 160 ◽  
pp. 108366
Author(s):  
Patrick F. O’Rourke ◽  
Scott D. Ramsey ◽  
Brian A. Temple
Keyword(s):  
Lie Group ◽  
Group Analysis ◽  
Reactor Neutron ◽  
Lie Group Analysis ◽  
Neutron Kinetics
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