scholarly journals Temperature and void reactivity coefficient calculations for the high flux isotope reactor safety analysis report

1994 ◽  
Author(s):  
W.W. Jr. Engle ◽  
L.R. Williams
Keyword(s):  
Safety Analysis ◽  
High Flux ◽  
Reactor Safety ◽  
Reactivity Coefficient

scholarly journals Fuel-Coolant-Interaction modeling and analysis work for the High Flux Isotope Reactor Safety Analysis Report

1993 ◽  
Author(s):  
R.P. Taleyarkhan ◽  
V. Georgevich ◽  
C.W. Nestor ◽  
S.J. Chang ◽  
J. Freels ◽  
...  
Keyword(s):  
Safety Analysis ◽  
High Flux ◽  
Reactor Safety ◽  
Modeling And Analysis ◽  
Interaction Modeling

Evaluation of computational fluid dynamic methods for reactor safety analysis (ECORA)

2005 ◽  
Vol 235 (2-4) ◽  
pp. 359-368 ◽  
Author(s):  
M. Scheuerer ◽  
M. Heitsch ◽  
F. Menter ◽  
Y. Egorov ◽  
I. Toth ◽  
...  
Keyword(s):  
Computational Fluid Dynamic ◽  
Fluid Dynamic ◽  
Safety Analysis ◽  
Reactor Safety ◽  
Dynamic Methods

scholarly journals MELT-III: a neutronics, thermal-hydraulics computer program for fast reactor safety analysis. Volume II

1974 ◽  
Author(s):  
A.E. Waltar ◽  
W.L. Partain ◽  
D.C. Kolesar ◽  
L.D. O'Dell ◽  
A. Jr. Padilla ◽  
...  
Keyword(s):  
Computer Program ◽  
Fast Reactor ◽  
Safety Analysis ◽  
Thermal Hydraulics ◽  
Reactor Safety

On-Line Sequestration of Fission Product Gases in Operating Nuclear Reactors

2010 ◽  
Author(s):  
Gary M. Sandquist ◽  
Jay F. Kunze
Keyword(s):  
Fission Product ◽  
Research Program ◽  
Molecular Sieves ◽  
Source Term ◽  
Nuclear Reactors ◽  
High Flux ◽  
Reactor Safety ◽  
Fuel Failure ◽  
Fuel Pin ◽  
On Line

A research program is outlined to theoretically and experimentally establish the effectiveness and acceptability of on-line sequestering of fission product gases (FPGs) as they are generated in a fissile fuel pin using adsorbents and/or molecular sieves selectively distributed within the lower spring-plenum region of the LWR fuel. If successful this innovation can be implemented in existing and next generation LWRs and may: • reduce accident source term (releasable FPGs); • enhance reactor safety and acceptance; • extend fuel life suppressing clad swelling and fuel failure; • reduce thermal neutron poisons in high flux core regions; • improve operational and economical performance; • require only minor changes to fuel pin assembly and use; • use in LWRs with no license or tech-specifications impact.

Application of a new drag coefficient model at CFD-simulations on free surface flows relevant for the nuclear reactor safety analysis

2012 ◽  
Vol 39 (1) ◽  
pp. 70-82 ◽  
Author(s):  
Deendarlianto ◽  
Thomas Höhne ◽  
Pavel Apanasevich ◽  
Dirk Lucas ◽  
Christophe Vallée ◽  
...  
Keyword(s):  
Free Surface ◽  
Drag Coefficient ◽  
Nuclear Reactor ◽  
Safety Analysis ◽  
Free Surface Flows ◽  
Reactor Safety ◽  
Cfd Simulations ◽  
Surface Flows ◽  
Nuclear Reactor Safety

Sensitivity Assessments in Reactor Safety Analysis

1977 ◽  
Vol 32 (2) ◽  
pp. 155-166
Author(s):  
J. E. Kelly ◽  
F. L. Leverenz ◽  
N. J. McCormick ◽  
R. C. Erdmann
Keyword(s):  
Safety Analysis ◽  
Reactor Safety

NUR research reactor safety analysis study for long time natural convection (NC) operation mode

2010 ◽  
Vol 240 (4) ◽  
pp. 823-831 ◽  
Author(s):  
M. Azzoune ◽  
L. Mammou ◽  
M.H. Boulheouchat ◽  
T. Zidi ◽  
M.Y. Mokeddem ◽  
...  
Keyword(s):  
Natural Convection ◽  
Research Reactor ◽  
Operation Mode ◽  
Safety Analysis ◽  
Reactor Safety ◽  
Analysis Study ◽  
Long Time
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