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<title>Journal of Nuclear Engineering and Radiation Science</title>
<link>http://yetl.yabesh.ir/yetl1/handle/yetl/19049</link>
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<pubDate>Sat, 04 Apr 2026 08:48:25 GMT</pubDate>
<dc:date>2026-04-04T08:48:25Z</dc:date>
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<title>Journal of Nuclear Engineering and Radiation Science</title>
<url>http://localhost:80/yetl1/bitstream/id/184258/</url>
<link>http://yetl.yabesh.ir/yetl1/handle/yetl/19049</link>
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<title>Adjuster Absorber Rods Return to Service at PLNGS</title>
<link>http://yetl.yabesh.ir/yetl1/handle/yetl/4310390</link>
<description>Adjuster Absorber Rods Return to Service at PLNGS
Krishnamoorthy, J.; Deveaux, D.; Mullin, D.; Usalp, E. C.; Sun, L.; Sharpe, J.; Rouben, D.
The original CANDU® 600 design utilizes adjuster absorber (AA) rods to flatten the flux shape in the reactor core optimize power output, compensate for fuel burnup, provide excess reactivity to overcome 135Xe buildup following a power reduction, and allow for reactivity shim. At Point Lepreau Nuclear Generating Station (PLNGS) in 1999, adjuster absorber banks 6 and 7 were locked in the reactor core and removed from service. Later in 2019, adjuster absorber banks 1–5 were placed on manual. Since then, a significant program was put in place to restore adjuster banks 1–6 to service, which was successfully completed in October 2023. Adjuster absorber bank 7 remains locked in-core. This paper summarizes the rationale for removing the PLNGS adjuster absorbers from service, the effort required for their restoration, applicable lessons learned, and next steps.
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<pubDate>Wed, 01 Jan 2025 00:00:00 GMT</pubDate>
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<dc:date>2025-01-01T00:00:00Z</dc:date>
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<title>Radiological Diversification in Indoor Radon and Thoron Levels in Correlations With Various Factors in Residential Dwellings</title>
<link>http://yetl.yabesh.ir/yetl1/handle/yetl/4310379</link>
<description>Radiological Diversification in Indoor Radon and Thoron Levels in Correlations With Various Factors in Residential Dwellings
Mittal, Sudhir
Human exposure to indoor radon, thoron, and their progenies has become a serious problem throughout the world. In the current research, assessment of indoor radon and thoron and their effect on human beings have been analyzed from 200 various locations (five samples from each location) of Jodhpur, Jhunjhunu, Bikaner, and Nagaur districts of Northern Rajasthan, India made with the help of RAD7 technique. The radon and thoron levels inside the houses of indoor air vary from 10.75 to 90 Bq m−3 and 18.65 to 210 Bq m−3, respectively. The calculated values of all dwellings of indoor radon concentration are lower than the action limit provided by the International Commission on Radiological Protection (ICRP). The results calculated from absorbed dose rate to lungs, equivalent dose to lungs, effective dose to specific parts of lungs tracheobronchial, pulmonary + pulmonary lymph region, overall lung dose due to 222Rn and 220Rn exposure, annual effective dose, excess life time cancer risk (ELCR), and lung cancer cases per year per million people (LCC) due to radon and thoron level and their risk due to exposure are also discussed. In this study, we also examined the risk effect due to radon and thoron correlated with building material and ventilation conditions.
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<pubDate>Wed, 01 Jan 2025 00:00:00 GMT</pubDate>
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<dc:date>2025-01-01T00:00:00Z</dc:date>
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<title>Study of TRICO II Reactor Startup and Shutdown Operations Using the OpenMC Calculation Code</title>
<link>http://yetl.yabesh.ir/yetl1/handle/yetl/4310368</link>
<description>Study of TRICO II Reactor Startup and Shutdown Operations Using the OpenMC Calculation Code
Mweze, E. B.; Muswema, J. L.; Ekoko, G. B.; Kom'bele, D. G.
Nuclear reactor startup and shutdown procedures must be carried out with great care and efficiency. To ensure correct reactor operation, it is crucial to make and maintain the reactor critical during startup and subcritical during shutdown. In this paper, OpenMC computer code was used to model the TRICO II research reactor and simulate its startup and shutdown operations. Positions of the four control rods (transient rod, safety rod, regulating rod, and shim rod) were varied along positive z-axis for startup and negative z-axis for shutdown. The reactivity results obtained were compared with those of standard reactor startup and shutdown operations. This technique optimizes the probability of a better startup or shutdown operation and avoids wasting resources on trial-and-error testing.
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<pubDate>Wed, 01 Jan 2025 00:00:00 GMT</pubDate>
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<dc:date>2025-01-01T00:00:00Z</dc:date>
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<title>Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor</title>
<link>http://yetl.yabesh.ir/yetl1/handle/yetl/4310363</link>
<description>Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor
Nava Dominguez, A.; Huang, Xianmin; Gaudet, Michel; Khumsa-Ang, Kittima; Mendoza España, Alberto D'Ansi; Chow, Jimmy; Roubtsov, Danila; Namburi, Hygreeva
The supercritical water-cooled reactor (SCWR) is one of the six concepts selected by the generation-IV international forum (GIF) for future research. This technology is a natural evolutionary step of the current water-cooled reactors. Canada is a participant of the GIF, and under this international endeavor developed the Canadian SCWR, which is a 1200 MWe concept. However, due to high capital cost associated with building large units, the nuclear industry rekindled an old concept: Small reactors (SRs), and now small modular reactors (SMRs). These reactors are poised to reduce the financial risks associated with large units, and also potentially offer more flexibility as modules can be prefabricated and transported to the construction site for assembly. As a result, numerous domestic and international programs were established to support the development and deployment of SMRs. The ECC-SMART project was proposed to develop a supercritical water-cooled SMR. Canada joined this collaboration, and under this project alongside the GIF SCWR and IAEA CRP platforms, a new Canadian supercritical water-cooled small modular reactor (SCW-SMR) was proposed and developed. This concept is based on the experience and lessons learned during the development of the Canadian SCWR. An overview of a multidisciplinary approach that led to the concept is presented in this paper, consisting of a market study, thermodynamics and energy conversion, reactor physics, thermal hydraulics, materials and chemistry, and safety assessments.
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<pubDate>Wed, 01 Jan 2025 00:00:00 GMT</pubDate>
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<dc:date>2025-01-01T00:00:00Z</dc:date>
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