Investigation of primary cooling water chemistry following the partial meltdown of Pu–Be neutron source in Tehran Research Reactor Core (TRR)

2011 ◽  
Vol 241 (3) ◽  
pp. 688-692
Author(s):  
Reza Gholizadeh Aghoyeh ◽  
Hossein Khalafi
2013 ◽  
Vol 28 (1) ◽  
pp. 18-24
Author(s):  
Sayedeh Mirmohammadi ◽  
Morteza Gharib ◽  
Parnian Ebrahimzadeh ◽  
Reza Amrollahi

A hot water layer system (HWLS) is a novel system for reducing radioactivity under research reactor containment. This system is particularly useful in pool-type research reactors or other light water reactors with an open pool surface. The main purpose of a HWLS is to provide more protection for operators and reactor personnel against undesired doses due to the radio- activity of the primary loop. This radioactivity originates mainly from the induced radioactivity contained within the cooling water or probable minute leaks of fuel elements. More importantly, the bothersome radioactivity is progressively proportional to reactor power and, thus, the HWLS is a partial solution for mitigating such problems when power upgrading is planned. Following a series of tests and checks for different parameters, a HWLS has been built and put into operation at the Tehran research reactor in 2009. It underwent a series of comprehensive tests for a period of 6 months. Within this time-frame, it was realized that the HWLS could provide a better protection for reactor personnel against prevailing radiation under containment. The system is especially suitable in cases of abnormality, e. g. the spread of fission products due to fuel failure, because it prevents the mixing of pollutants developed deep in the pool with the upper layer and thus mitigates widespread leakage of radioactivity.


2014 ◽  
Vol 90 ◽  
pp. 132-137 ◽  
Author(s):  
Yaser Kasesaz ◽  
Hossein Khalafi ◽  
Faezeh Rahmani ◽  
Arsalan Ezati ◽  
Mehdi Keyvani ◽  
...  

Author(s):  
Zeyun Wu

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.


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