Evaluation of GTHTR300A nuclear power plant design with dry cooling

Summary Most of the small modular reactor (SMR) concepts developed in the past have compact size and a longer life reactor core than the conventional nuclear power plants. However, these concepts have not achieved the full modularization including power conversion system. This study suggests an innovative concept of a reactor cooled by supercritical state carbon dioxide (S‐CO2). A reactor core with uranium carbide fuel controlled by drum type control rods was designed. The core has long life (20 years) without refueling or reshuffling as well as inherent safety features. The reactor can be used as a distributed power source and replace outdated fossil fuel power plants for small cities. Moreover, the authors propose the S‐CO2 Brayton cycle as a power conversion system to achieve compact and lightweight module. Because of compact core and power conversion system, the entire system can be contained in a single module. The target of the system is to be able to transport a single core and power conversion system module via ground transportation. In order to meet this target, single module's total weight is minimized in the order of 100 tons. The external size of a module is less than 7 m in length and 4 m in diameter. It produces 12MWe electricity from 36MWt reactor core. The S‐CO2 Brayton cycle was optimized, and the cycle components such as turbomachineries and heat exchangers were designed preliminarily to observe the potential to maximize the performance while minimizing the weight. Moreover, a dry air‐cooling option to reject waste heat for inland installation was selected for the suggested nuclear system. A concept of passive decay heat removal system was developed, and its performance was examined to determine the required heat removal capacity of the system to assure the system's safety under various anticipated accidents. Copyright © 2016 John Wiley & Sons, Ltd.

Section: Design Of Dry Air Cooling Heat Exchangermentioning

confidence: 99%

A concept design of supercritical CO₂cooled SMR operating at isolated microgrid region

Kim

Moon

et al. 2016

“…This paper presents a core concept for a new small modular sodium-cooled fast reactor (SMSFR) that combines the advantages of the sodium-cooled fast reactor (SFR) and the small modular reactor (SMR). The SFR is one of the Generation IV reactor concepts [1][2][3][4][5]. Many SFR concepts have been proposed to achieve a long-life core by adopting a fast spectrum [6][7][8][9][10].…”

Section: Introductionmentioning

confidence: 99%

Design study of long-life small modular sodium-cooled fast reactor

Park

Tak

Kim

et al. 2016

Summary This paper presents a new design for a small modular sodium‐cooled fast reactor core with an optimized lifetime and reactivity swing through the analysis of various breed‐and‐burn strategies and its neutronic analyses in terms of active core movements, isotopic mass balance, kinetic parameters, and inherent safety. The new core design aims at a power level of 260 MW with a long lifetime of 30 years without refueling and a reactivity swing smaller than 1000 pcm. Starting from five initial candidate cores with various breed‐and‐burn strategies, an optimum core was selected from a combination of the two candidates that shows a proper breeding behavior with the optimized uranium enrichment in the low‐enriched uranium region and the optimized size of the blanket region. The depletion analysis of the new core provides various reactor design parameters such as the core multiplication factor, breeding ratio, heavy metal mass change, power distribution, and summary of neutron balance. In addition, the perturbation analysis provides the reactor kinetic parameters and reactivity feedback coefficients for the inherent safety analysis of the core. The integral reactivity parameters of the quasi‐static reactivity balance analysis demonstrate that the new core is inherently safe in cases of unprotected loss of flow, unprotected loss of heat sink, and unprotected transient over power. Copyright © 2016 John Wiley & Sons, Ltd.

“…The development in field of nuclear plants/reactors coupled with desalination processes is still progressing, opening up possibilities of cutting edge research. Optimization of the coupling processes will influence the direction of potable water production in the future, establishing the role of sustainable energy in ‘new water’ generation . Recent work and study on nuclear desalination show that the integration of conventional desalination plants with nuclear installations is practicable and is now a developed technology that can be beneficial for meeting the fresh water demands worldwide.…”

Section: Introductionmentioning

confidence: 99%

Theoretical calculation simulation studies of ABV nuclear reactor coupled with desalination system

Khan

Danish

Haider

et al. 2015

Summary In this paper, research has been conducted on the floating type nuclear power plant named as ABV reactor which is designed for district heating, power, and sea water desalination by OKBM facility at Russia. This reactor was tested under different thermal loads during the designing phase, and three modules have been investigated. Theoretical calculations and simulation studies have been performed on these three modules having specifications as ABV‐6M with 47MWth, ABV‐6 with 38MWth, and ABV‐3 with 18MWth.The results obtained from these modules have been calculated mathematically and verified by simulation. We have compared the originally derived data of ABV desalination system with our theoretical and simulation analysis. The results from two desalination techniques including RO and RO + MED have been calculated and are presented in this paper with details. The results obtained from both analysis show that the efficiency of ABV nuclear reactor desalination system increases with the decrease in corresponding water cost ratio. Copyright © 2015 John Wiley & Sons, Ltd.