Study on void fraction distribution in the moderator cell of Cold Neutron Source systems in China Advanced Research Reactor

2007 ◽  
Vol 393 (1-2) ◽  
pp. 336-346 ◽  
Author(s):  
Liangxing Li ◽  
Huixiong Li ◽  
Jinfeng Hu ◽  
Qincheng Bi ◽  
Tingkuan Chen
Keyword(s):  
Neutron Source ◽  
Void Fraction ◽  
Research Reactor ◽  
Cold Neutron ◽  
Cold Neutron Source ◽  
Void Fraction Distribution ◽  
Fraction Distribution ◽  
Moderator Cell

Thermo-hydraulic test of the moderator cell of LH2 cold neutron source at BNC

2000 ◽  
Vol 276-278 ◽  
pp. 214-215 ◽  
Author(s):  
T. Grósz ◽  
T. Hargitai ◽  
V.A. Mityukhlyaev ◽  
L. Rosta ◽  
A.P. Serebrov ◽  
...  
Keyword(s):  
Neutron Source ◽  
Cold Neutron ◽  
Hydraulic Test ◽  
Cold Neutron Source ◽  
Moderator Cell

Self-regulating characteristics of a cold neutron source with a cylindrical-annulus moderator cell

2002 ◽  
Vol 311 (1-2) ◽  
pp. 164-172 ◽  
Author(s):  
Takeshi Kawai ◽  
Hirofumi Yoshino ◽  
Yuji Kawabata ◽  
Masahiro Hino ◽  
Chien-Hsiung Lee ◽  
...  
Keyword(s):  
Neutron Source ◽  
Cold Neutron ◽  
Cylindrical Annulus ◽  
Cold Neutron Source ◽  
Moderator Cell

Liquid hydrogen cold neutron source in operation. at the Budapest Research Reactor

2002 ◽  
Vol 74 (0) ◽  
pp. s240-s242 ◽  
Author(s):  
L. Rosta ◽  
T. Gr�sz ◽  
T. Hargitai
Keyword(s):  
Neutron Source ◽  
Research Reactor ◽  
Cold Neutron ◽  
Liquid Hydrogen ◽  
Cold Neutron Source

Thermal and mechanical characteristics of the moderator cell in a cold neutron source

2012 ◽  
Vol 50 ◽  
pp. 1-7 ◽  
Author(s):  
Shuo Sun ◽  
Yuntao Liu ◽  
Hongli Wang ◽  
Dongfeng Chen ◽  
Quanke Feng ◽  
...  
Keyword(s):  
Neutron Source ◽  
Mechanical Characteristics ◽  
Cold Neutron ◽  
Cold Neutron Source ◽  
Moderator Cell

A Research Reactor Core Design for Advance Neutron Source

2017 ◽  
Author(s):  
Zeyun Wu
Keyword(s):  
Neutron Source ◽  
Research Reactor ◽  
Cold Neutron ◽  
Thermal Flux ◽  
Thermal Power ◽  
Reactor Core ◽  
Operating Cycle ◽  
Start Up ◽  
Cold Neutron Source ◽  
Pool Type

This paper presents the recent neutronics analysis results of a proposed LEU-fueled research reactor. The main goal of the research reactor is to provide advanced neutron source with a particular emphasis on high intensity cold neutron sources. A tank-in-pool type reactor with an innovative horizontally split compact core was developed in order to maximize the yield of the thermal flux trap in the reflector area. The reactor was designed with 20 MW thermal power and 30-day operating cycle. For non-proliferation purposes, the LEU fuel (U3Si2-Al) with 19.75 wt.% enrichment was used. The estimated maximum thermal flux of the reactor is ∼5×1014 n/cm2-s. The total peaking factor of the start-up (SU) core is ∼2.5. The calculated brightness of the cold neutron source (CNS) demonstrates the superiority of the cold neutron performance of the design.

scholarly journals Using CFD as Preventative Maintenance Tool for the Cold Neutron Source Thermosiphon System

2016 ◽  
Vol 2016 ◽  
pp. 1-11
Author(s):  
Mark Ho ◽  
Yeongshin Jeong ◽  
Haneol Park ◽  
Guan Heng Yeoh ◽  
Weijian Lu
Keyword(s):  
Natural Convection ◽  
Neutron Source ◽  
Cold Neutron ◽  
Numerical Models ◽  
Normal Operation ◽  
Transient Condition ◽  
Decay Heat ◽  
Experimental Heat ◽  
Cold Neutron Source ◽  
Moderator Cell

The cold neutron source (CNS) system of the Open Pool Australian Light-Water (OPAL) reactor is a 20 L cryogenically cooled liquid deuterium thermosiphon system. The CNS is cooled by forced convective helium which is held at room temperature during stand-by (SO) mode and at ~20 K during normal operation (NO) mode. When helium cooling stops, the reactor is shut down to prevent the moderator cell from overheating. This computational fluid dynamics (CFD) study aims to determine whether the combined effects of conduction and natural convection would provide sufficient cooling for the moderator cell under the influence of reactor decay heat after reactor shutdown. To achieve this, two commercial CFD software packages using an identical CFD mesh were first assessed against an experimental heat transfer test of the CNS. It was found that both numerical models were valid within the bounds of experimental uncertainty. After this, one CFD model was used to simulate the thermosiphon transient condition after the reactor is shut down. Two independent shutdown conditions of different decay-heat power profiles were simulated. It was found that the natural convection and conduction cooling in the thermosiphon were sufficient for dissipating both decay-heat profiles, with the moderator cell remaining below the safe temperature of 200°C.

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