The authors' replies to the discussion on “The application of digital computers to nuclear-reactor design”, “Temperature transients in gas-cooled thermal nuclear reactors”, “The design, performance and use of fission counters” and “Boron trifluoride proportional counters”

1958 ◽  
Vol 105 (22) ◽  
pp. 368-369
Author(s):  
J. Howlett ◽  
J.H. Bowen ◽  
E.F.O. Masters ◽  
W. Abson ◽  
P.G. Salmon ◽  
...  
Keyword(s):  
Boron Trifluoride ◽  
Nuclear Reactor ◽  
Nuclear Reactors ◽  
Reactor Design ◽  
Design Performance ◽  
Proportional Counters ◽  
Digital Computers

Thermal Aspects of Using Thoria Fuel in SuperCritical Water-Cooled Nuclear Reactors

2009 ◽  
Author(s):  
Lisa Grande ◽  
Bryan Villamere ◽  
Adrianexy Rodriguez-Prado ◽  
Sally Mikhael ◽  
Leyland Allison ◽  
...  
Keyword(s):  
Thermal Conductivity ◽  
Supercritical Water ◽  
Alternative Fuels ◽  
Nuclear Reactor ◽  
Nuclear Reactors ◽  
Reactor Design ◽  
Operating Conditions ◽  
Thermal Design ◽  
Suitable Alternative ◽  
Design Options

SuperCritical Water-cooled Reactors (SCWRs) are one of six next-generation nuclear-reactor design options under consideration worldwide. These nuclear-reactor design options are included in the major international treaties such as: Generation IV International Forum (GIF) and INternational PROject on innovative nuclear reactors and fuels (INPRO). SCWR coolant is light water, which operates at supercritical pressures and temperatures. Typical SCWR coolant operating parameters are 25 MPa and 350–625°C. These SCWR operating conditions significantly increase the thermal efficiency of a SCW Nuclear Power Plant (NPP) (about 45 – 50%) compared to that of existing NPPs (30 – 35%). Also, SCWRs use significantly higher water parameters than existing water-cooled reactors, because of this they can support hydrogen co-generation. Previous thermal-design fuel-channel option studies for SCWRs have shown that the use of uranium dioxide (UO2) fuel at supercritical water conditions might be unacceptable as the fuel centerline temperature is close to or even exceeds the industry accepted limit of 1850°C. Alternative fuels with a higher thermal conductivity have to be considered. Thoria (ThO2) fuel is a suitable alternative to UO2 due to its higher thermal conductivity. Thoria fuel is beneficial because it complies with the Non-Proliferation Treaty and there are plenty of reserves worldwide. Therefore, ThO2 fuel and its suitability with SCWR use are considered in this paper.

Japan's Post-Fukushima Energy Politics

2015 ◽  
Vol 07 (02) ◽  
pp. 109-116
Author(s):  
Tai Wei LIM
Keyword(s):  
Democratic Party ◽  
Nuclear Reactor ◽  
Prime Minister ◽  
Nuclear Reactors ◽  
Liberal Democratic Party ◽  
The Political ◽  
Political Arena ◽  
Liberal Democratic ◽  
Energy Politics ◽  
Gubernatorial Election

A 2011 earthquake damaged the Fukushima nuclear reactor and provided a galvanising point for anti-nuclear resistance groups in Japan. Their public cause slowly faded from the political arena after the Democratic Party of Japan fell out of power and anti-nuclear politicians lost the 2014 Tokyo gubernatorial election. The current Liberal Democratic Party Prime Minister Abe holds a pro-nuclear position and urges the reactivation of Japan's nuclear reactors after all safeguards have been satisfied.

Computers in nuclear-reactor design

1958 ◽  
Vol 4 (41) ◽  
pp. 249-251
Author(s):  
J. Howlett
Keyword(s):  
Nuclear Reactor ◽  
Reactor Design

Exploring the Use of Alumina Nanofluid as Emergency Coolant for Nuclear Fuel Bundle

2018 ◽  
Vol 11 (2) ◽  
Author(s):  
A. S. Chinchole ◽  
Arnab Dasgupta ◽  
P. P. Kulkarni ◽  
D. K. Chandraker ◽  
A. K. Nayak
Keyword(s):  
Heat Transfer ◽  
Nuclear Fuel ◽  
Nuclear Reactor ◽  
Cooling System ◽  
Nuclear Reactors ◽  
Electrical Heating ◽  
High Dose ◽  
Potential Candidate ◽  
Alumina Nanofluid ◽  
Core Cooling

Abstract Nanofluids are suspensions of nanosized particles in any base fluid that show significant enhancement of their heat transfer properties at modest nanoparticle concentrations. Due to enhanced thermal properties at low nanoparticle concentration, it is a potential candidate for utilization in nuclear heat transfer applications. In the last decade, there have been few studies which indicate possible advantages of using nanofluids as a coolant in nuclear reactors during normal as well as accidental conditions. In continuation with these studies, the utilization of nanofluids as a viable candidate for emergency core cooling in nuclear reactors is explored in this paper by carrying out experiments in a scaled facility. The experiments carried out mainly focus on quenching behavior of a simulated nuclear fuel rod bundle by using 1% Alumina nanofluid as a coolant in emergency core cooling system (ECCS). In addition, its performance is compared with water. In the experiments, nuclear decay heat (from 1.5% to 2.6% reactor full power) is simulated through electrical heating. The present experiments show that, from heat transfer point of view, alumina nanofluids have a definite advantage over water as coolant for ECCS. Additionally, to assess the suitability of using nanofluids in reactors, their stability was investigated in radiation field. Our tests showed good stability even after very high dose of radiation, indicating the feasibility of their possible use in nuclear reactor heat transfer systems.

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