scholarly journals Experimental investigation of sodium boiling heat exchange in fuel subassembly mockup for perspective fast reactor safety justification

2015 ◽  
Vol 2015 (3) ◽  
pp. 85-96
Author(s):  
Ruslan Rashitovich Khafizov ◽  
Vladimir Mikhaylovich Poplavsky ◽  
Valery Ivanovich Rachkov ◽  
Aleksandr Pavlovich Sorokin ◽  
Yurij Mikhaylovich Ashurko ◽  
...  
Keyword(s):  
Experimental Investigation ◽  
Heat Exchange ◽  
Fast Reactor ◽  
Reactor Safety

scholarly journals Experimental investigation of sodium boiling heat exchange in fuel subassembly mockup for perspective fast reactor safety substantiation

2015 ◽  
Vol 1 (2) ◽  
pp. 147-152 ◽  
Author(s):  
R.R. Khafizov ◽  
V.M. Poplavsky ◽  
V.I. Rachkov ◽  
A.P. Sorokin ◽  
Yu.M. Ashurko ◽  
...  
Keyword(s):  
Experimental Investigation ◽  
Heat Exchange ◽  
Fast Reactor ◽  
Reactor Safety

scholarly journals AR-1 experimental model and facility preparation for the purpose of experimental investigation of sodium boiling in fuel subassembly mockup for new generation fast reactor safety justification

2014 ◽  
Vol 2014 (1) ◽  
pp. 77-87
Author(s):  
Ruslan Rashitovich Khafizov ◽  
Yurij Mikhaylovich Ashurko ◽  
Andrey Vikent’evich Volkov ◽  
Evgeny Fyodorovich Ivanov ◽  
Vitalij Vladimirovich Privezentsev ◽  
...  
Keyword(s):  
Experimental Investigation ◽  
Experimental Model ◽  
Fast Reactor ◽  
Reactor Safety ◽  
New Generation

scholarly journals Fast reactor safety and the fire at Beloyarsk

Nature ◽  
1980 ◽  
Vol 284 (5751) ◽  
pp. 10-10
Author(s):  
R.D. SMITH
Keyword(s):  
Fast Reactor ◽  
Reactor Safety

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

New Reactor Safety Measures for the European Sodium Fast Reactor - Part I: Conceptual Design

2021 ◽  
Author(s):  
Joel Guidez ◽  
Janos Bodi ◽  
Konstantin Mikityuk ◽  
Enrico Girardi ◽  
Bernard Carluec
Keyword(s):  
Fast Reactor ◽  
Heat Removal ◽  
Thermal Inertia ◽  
Lessons Learned ◽  
Reactor Safety ◽  
Fukushima Accident ◽  
Safety Level ◽  
Safety Measures ◽  
Sodium Fast Reactor ◽  
High Thermal Inertia

Abstract Following up the previous CP-ESFR project, the ESFR-SMART project considers the safety objectives envisaged for Generation-IV reactors, taking into account the lessons learned from the Fukushima accident, in order to increase the safety level of the European Sodium Fast Reactor (ESFR). In accordance with these objectives, guidelines have been defined to drive the ESFR-SMART developments, mainly simplifying the design and using all the positive features of Sodium Fast Reactors (SFR), such as low coolant pressure, efficiency of natural convection, possibility of decay heat removal (DHR) by atmospheric air, high thermal inertia and long grace period before a human intervention is needed. In this paper, a set of new ambitious safety measures is introduced for further evaluation within the project. The proposed set aims at consistency with the main lines of safety evolutions since the Fukushima accident, but it does not yet constitute the final comprehensive safety analysis. The paper gives a first review of the new propositions to enhance the ESFR safety, leading to a simplified reactor, forgiving and including a lot of passivity. This first version is supported by the various project tasks in order to assess the relevance of the whole design in comparison to the final safety objectives.

scholarly journals Experimental investigation of the heat exchange intensity

2018 ◽  
Vol 245 ◽  
pp. 07002 ◽  
Author(s):  
Vladimir Davletbaev ◽  
Natalia Rydalina ◽  
Elena Antonova
Keyword(s):  
Experimental Investigation ◽  
Heat Exchange ◽  
Heat Exchangers ◽  
Exchange Process ◽  
Porous Metal ◽  
Experimental Setup ◽  
Working Medium ◽  
Refrigeration Unit ◽  
Heat Exchange Process ◽  
Exchange Intensity

We study heat exchangers at the experimental setup aiming at the energy-saving. The feature of this heat exchange process is of the fact that the working medium is a porous metal. The pores are filled with freon and operation of the refrigeration unit condenser is studied. The scheme of the experimental setup and experiment methodology are given. The results of the experiment and its processing are also presented.

Fuel behavior aspects of the interpretation of the SCARABEE fast reactor safety experiments

1980 ◽  
Vol 59 (2) ◽  
pp. 275-286 ◽  
Author(s):  
F. Schmitz ◽  
J.R. Matthews ◽  
H. Elbel ◽  
L. Roche ◽  
M. deFranco ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Reactor Safety ◽  
Fuel Behavior
Sign in / Sign up

Export Citation Format

Share Document