On the Corrosion of Spent Fuel Aluminium Cladding During Wet Storage

2008 ◽  
Vol 59 (2) ◽  
pp. 178-180
Author(s):  
Cristina Ciuculescu ◽  
Tanase Dobre
Keyword(s):  
Chemical Analysis ◽  
Water Samples ◽  
Research Reactor ◽  
Spent Fuel ◽  
Fuel Cladding ◽  
Storage Pool ◽  
Wet Storage ◽  
Spent Fuel Storage ◽  
Fuel Storage

The paper presents the results obtained from the curves curent-potential when Al-Mg3 samples polarization occurs in solutions that simulate the water from the storage pool. The samples used in research are characteristic for the fuel spent C-36 and EK-10 and also for the storage pool from the Magurele- Romania research reactor deactivation. The study is unique due to the material samples used and due to the fact that the results of electrochemical experiments are correlated to the results from the chemical analysis of water samples from spent fuel storage basins. The paper is in the class of those which serve to the estimation of the dynamics of the degradation of spent fuel cladding during wet storage.

scholarly journals Study of corrosion of aluminium alloys of nuclear purity in ordinary water, пart one

2004 ◽  
Vol 19 (2) ◽  
pp. 77-93 ◽  
Author(s):  
Milan Pesic ◽  
Tatjana Maksin ◽  
Gabrijela Jordanov ◽  
Rajko Dobrijevic ◽  
Zoja Idjakovic
Keyword(s):  
Aluminum Alloys ◽  
Research Reactor ◽  
Initial Study ◽  
Spent Fuel ◽  
Energy Agency ◽  
Ordinary Water ◽  
Storage Pool ◽  
Spent Fuel Storage ◽  
Fuel Storage ◽  
Frame Work

Effects of corrosion of aluminum alloys of nuclear purity in ordinary water of the spent fuel storage pool of the RA research reactor at VINCA Institute of Nuclear Sciences has been examined in the frame work of the International Atomic Energy Agency Coordinated Research Project "Corrosion of Research Reactor Aluminum-Clad Spent Fuel in Water" since 2002. The study presented in this paper comprises activities on determination and monitoring of chemical parameters and radio activity of water and sludge in the RA spent fuel storage pool and results of the initial study of corrosion effects obtained by visual examinations of surfaces of various coupons made of aluminum alloys of nuclear purity of the test racks exposed to the pool water for a period from six months to six years.

Study on Radiation Dose Calculation of PWR Spent Fuel Storage and Transportation

2021 ◽  
Author(s):  
Wen Yang ◽  
Xing Li ◽  
Jinrong Qiu ◽  
Lun Zhou
Keyword(s):  
Radiation Dose ◽  
Normal Condition ◽  
Radiation Safety ◽  
Spent Fuel ◽  
Dose Rates ◽  
Storage Pool ◽  
Transport Container ◽  
Photon Dose ◽  
Spent Fuel Storage ◽  
Fuel Storage

Abstract With the rapid development of nuclear energy, spent fuel will accumulate in large quantities. Spent fuel is generally cooled and placed in a storage pool, and then transported to a reprocessing plant at an appropriate time. Because spent fuel is content with a high level of radiation, spent fuel storage and transportation safety play important roles in the nuclear safety. Radiation dose safety are checked and validated using source analysis and Monte Carlo method to establish a radiation dose rate calculation model for PWR spent fuel storage pool and transport container. The calculation results show that the neutron and photon dose rates decrease exponentially with increase of water level under normal condition of storage pool. The attenuation multiples of neutron and photon dose rates are 4.64 and 1.59, respectively. According to radiation dose levels in different water height situations, spent fuel pool under loss of coolant accident can be divides into five workplaces. They are supervision zone, regular zone, intermittent zone, restricted zone and radiation zone. Under normal condition of transport container, the dose rates at the surface of the container and at a distance of 1 m from the surface are 0.1759 mSv/h and 0.0732 mSv/h, respectively. The dose rates decrease with the increasing radius of break accident, and dose rate at the surface of the transport container is 0.278 mSv/h when the break radius is 20 cm. Transport container conforms to the radiation safety standards of International Atomic Energy Agency (IAEA). This study can provide some reference for radiation safety analysis of spent fuel storage and transportation.

Criticality safety of the ET-RR-1 new spent fuel storage pool

2001 ◽  
Vol 28 (4) ◽  
pp. 375-383 ◽  
Author(s):  
E. Massoud ◽  
O.H. Sallam ◽  
E. Amin
Keyword(s):  
Spent Fuel ◽  
Storage Pool ◽  
Spent Fuel Storage ◽  
Fuel Storage ◽  
Criticality Safety

Direct estimation of 90Sr in water samples of spent fuel storage bay using partial counting rate technique

2014 ◽  
Vol 300 (1) ◽  
pp. 89-92
Author(s):  
Amar Dutt Pant ◽  
S. Anilkumar ◽  
Vandana Pulhani ◽  
R. M. Tripathi ◽  
D. N. Sharma
Keyword(s):  
Water Samples ◽  
Counting Rate ◽  
Spent Fuel ◽  
Direct Estimation ◽  
Spent Fuel Storage ◽  
Fuel Storage

Evaluation of Radiation Effects on Residents Living Around the NSRR Under External Hazards

2020 ◽  
Vol 6 (2) ◽  
Author(s):  
Yuiko Motome ◽  
Yoshiya Akiyama ◽  
Hiroyuki Murao
Keyword(s):  
Radiation Effects ◽  
Research Reactor ◽  
Reactor Core ◽  
Fission Products ◽  
Internal Exposure ◽  
Spent Fuel ◽  
Loss Of Function ◽  
Safety Research ◽  
Spent Fuel Storage ◽  
Fuel Storage

Abstract The nuclear safety research reactor (NSRR) is a research reactor of training research isotopes general atomics—annular core pulse reactor (TRIGA-ACPR) type, located in the Nuclear Science Research Institute (NSRI). The NSRR facility has been utilized for fuel irradiation experiments to study the behaviors of nuclear fuels under reactivity-initiated accident (RIA) conditions. Under the new regulation standards, which was established after the Fukushima Daiichi accident, research reactors are regulated based on the risk of the facilities. The graded approach is introduced in the regulation. To apply the graded approach, the radiation effects on residents living around the NSRR under the external hazards were evaluated, and the level of the risk of the NSRR facility was investigated. This paper summarizes the result of the evaluation in the case where the safety functions are lost due to a tornado, an earthquake followed by a tsunami. There is fuel in the reactor core, fresh fuel storage, and spent fuel storage. As the effects from reactor core, we evaluate the external exposure to radiation and exposure from the release of fission products assuming that loss of function to shut down the reactor, break of cladding tubes, loss of reactor pool water, and collapse of the reactor building. As the effects from fresh fuel storage, we evaluate the internal exposure assuming that the fresh fuel particles released into the air because of breaking into pieces. In addition, we evaluate the critical safety assuming that the critical safety shapes of the fresh fuel storage are lost. As the effects from spent fuel storage, we evaluate the critical safety assuming that the critical safety shapes of the spent fuel storage are lost. All in all, the risk is confirmed to be relatively low, since the effective dose on the residents is found to be below 5 mSv per event due to the loss of the safety functions caused by the tornado, earthquake, and the accompanying tsunami.

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