Assessment of the high temperature fission chamber technology for the French fast reactor program

2011 ◽  
Author(s):  
C. Jammes ◽  
P. Filliatre ◽  
B. Geslot ◽  
T. Domenech ◽  
S. Normand
Keyword(s):  
High Temperature ◽  
Fast Reactor ◽  
Fission Chamber

Assessment of the High Temperature Fission Chamber Technology for the French Fast Reactor Program

2012 ◽  
Vol 59 (4) ◽  
pp. 1351-1359 ◽  
Author(s):  
Christian Jammes ◽  
Philippe Filliatre ◽  
Benoit Geslot ◽  
Thierry Domenech ◽  
Stephane Normand
Keyword(s):  
High Temperature ◽  
Fast Reactor ◽  
Fission Chamber

scholarly journals An Analysis of Methanol and Hydrogen Production via High-Temperature Electrolysis Using the Sodium Cooled Advanced Fast Reactor

2014 ◽  
Author(s):  
Shannon Bragg-Sitton ◽  
Richard Boardman ◽  
Robert Cherry ◽  
Wesley Deason ◽  
Michael McKellar
Keyword(s):  
High Temperature ◽  
Hydrogen Production ◽  
Fast Reactor ◽  
High Temperature Electrolysis

Conceptual Study of Neutron Physics of Nuclear Fuel Cycle for Ceramic Fast Reactor

2021 ◽  
Author(s):  
Xuesong Yan ◽  
Yaling Zhang ◽  
Yucui Gao ◽  
Lei Yang
Keyword(s):  
High Temperature ◽  
Nuclear Fuel ◽  
Fast Reactor ◽  
Spent Nuclear Fuel ◽  
Fuel Cycle ◽  
Fission Products ◽  
Nuclear Fuel Cycle ◽  
Purification Method ◽  
Neutron Physics ◽  
Conceptual Study

Abstract To make the nuclear fuel cycle more economical and convenient, as well as prevent nuclear proliferation, the conceptual study of a simple high-temperature dry reprocessing of spent nuclear fuel (SNF) for a ceramic fast reactor is proposed in this paper. This simple high-temperature dry (HT-dry) reprocessing includes the Atomics International Reduction Oxidation (AIROX) process and purification method for rare-earth elements. After removing the part of fission products from SNF by a HT-dry reprocessing without fine separation, the remaining nuclides and some uranium are fabricated into fresh fuel which can be used back to the ceramic fast reactor. Based on the ceramic coolant fast reactor, we studied neutron physics of nuclear fuel cycle which consists operation of ceramic reactor, removing part of fission products from SNF and preparation of fresh fuels for many time. The parameters of the study include effective multiplication factor (Keff), beam density, and nuclide mass for different ways to remove the fission products from SNF. With the increase in burnup time, the trend of increasing 239Pu gradually slows down, and the trend of 235U gradually decreases and become balanced. For multiple removal of part of fission products in the nuclear fuel cycle, the higher the removal, the larger the initial Keff.

scholarly journals Effect of Grain Size on High-Temperature Strength of Fast Reactor Spec. SUS316.

1997 ◽  
Vol 46 (11) ◽  
pp. 1274-1279 ◽  
Author(s):  
Yukio TAKAHASHI ◽  
Shingo DATE ◽  
Takanori NAKAZAWA
Keyword(s):  
Grain Size ◽  
High Temperature ◽  
Fast Reactor ◽  
High Temperature Strength

Research on the Stainless Steel Tubes and Pipes Material Standards of Demonstration Fast Reactor Power Plant

2013 ◽  
Author(s):  
Yaping Li ◽  
Guangdong Song
Keyword(s):  
Stainless Steel ◽  
High Temperature ◽  
Power Plant ◽  
Fast Reactor ◽  
Reactor Power ◽  
Steel Pipe ◽  
Thick Wall ◽  
Pipe Material ◽  
Stainless Steel Pipe ◽  
Reactor Power Plant

The main characteristics of the sodium pipe system in Demonstration Fast Reactor Power Plant (DFRPP) are high-temperature, thin-wall and big-caliber, which is different from high-pressure and thick-wall of the pressurized water reactor system, and the system is long-term operate in the environment of liquid metal sodium. How to guarantee the reliability of materials in high temperature are most important in material option. Engineering design depend on the criterion. Material standards are different in different countries, and corresponding construction codes are different too. Comparing the stainless steel pipe material standers at home and abroad and analyzing the material standards’ difference according to different construction codes, a stainless steel pipe material criterion system is put forward in this paper which is applicable for the DFRPP.

scholarly journals Characterization and localization of partial-discharge-induced pulses in fission chambers designed for sodium-cooled fast reactors

2018 ◽  
Vol 170 ◽  
pp. 03002
Author(s):  
G. Galli ◽  
H. Hamrita ◽  
C. Jammes ◽  
M.J. Kirkpatrick ◽  
E. Odic ◽  
...  
Keyword(s):  
High Temperature ◽  
Neutron Flux ◽  
Electrical Discharge ◽  
Partial Discharge ◽  
Electrical Signal ◽  
Fast Reactors ◽  
Electrode Gap ◽  
Fission Chamber ◽  
Flux Monitoring ◽  
Fission Chambers

During the operation of the Superphenix and Phenix reactors, an aberrant electrical signal was detected from the fission chambers used for neutron flux monitoring. This signal, thought to be due to partial electrical discharge (PD) is similar to the signal resulting from neutron interactions, and is generated in fission chambers at temperatures above 400 °C. This paper reports work on the characterization and localization of the source of this electrical signal in a High Temperature Fission Chamber (HTFC). The relation between the shape of the PD signal and various parameters (nature and pressure of the chamber filling gas, electrode gap distance, and fission chamber geometry) are first described. Next, experiments designed to identify the location within the chambers where the PD are being generated are presented. After verification and refinement of the results of these localization studies, it should be possible to propose changes to the fission chamber in order to reduce or eliminate the PD signal.

E217 Development of small fast reactor 4S : Development of large diameter high temperature electromagnetic pump

2009 ◽  
Vol 2009.14 (0) ◽  
pp. 463-466
Author(s):  
Yasuko Oyamatsu ◽  
Seiji Fujiwara ◽  
Rie Aizawa ◽  
Minoru funato ◽  
Hiroyuki Ota ◽  
...  
Keyword(s):  
High Temperature ◽  
Fast Reactor ◽  
Large Diameter ◽  
Electromagnetic Pump

Experimental Study on Sodium Column Fire of Sodium-Cooled Fast Reactor

2013 ◽  
Author(s):  
Kang-wei Peng ◽  
Zhi-gang Zhang ◽  
Ming Guo ◽  
Chao Wang ◽  
Shu-bin Sun
Keyword(s):  
High Temperature ◽  
Fast Reactor ◽  
Difficult Problem ◽  
Temperature Fields ◽  
Practical Significance ◽  
Liquid Sodium ◽  
Insulation Material ◽  
Reactor Accident ◽  
Temperature Liquid ◽  
Operation Pressure

In the operation of sodium-cooled fast reactor, accident caused by the leakage and combustion of liquid sodium is common, and it is a pivotal and difficult problem in research, construction and operation of sodium-cooled fast reactor internationally. In actual operation of sodium-cooled fast reactor, liquid sodium in sodium fire accident is difficult to form fog but mainly in columnar flow form due to low operation pressure and thermal insulation material wrapping the pipe, so experimental research about columnar fire is of much more practical significance. This paper focuses on combustion property on sodium column fire in the sodium-cooled fast reactor. Liquid sodium with high temperature will be poured into the combustion room via pouring high pressure nitrogen into sodium storage tank when solid sodium has been heated to enactment temperature; liquid sodium with high temperature will burn at combustion room with air forming sodium column fire. Initial temperature of sodium jet is about 200°C in experiment and spurt pressure is 0.2MPa, spurt flow is about 0.4–0.6m3 each hour. Temperature fields in combustion tank space and the catch plate in the bottom are measured through dozens of thermocouple distributed in combustion tank. No atomization phenomenon would exist in the pure sodium columnar fire in the space, the atomized fire triggered by splashed sodium from sodium stream striking the admittance plat and generate more than the high temperature of 900°C.

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