• Title/Summary/Keyword: nuclear power engineering

Search Result 3,827, Processing Time 0.039 seconds

Challenges in nuclear energy adoption: Why nuclear energy newcomer countries put nuclear power programs on hold?

  • Philseo Kim;Hanna Yasmine;Man-Sung Yim;Sunil S. Chirayath
    • Nuclear Engineering and Technology
    • /
    • 제56권4호
    • /
    • pp.1234-1243
    • /
    • 2024
  • The pressing need to mitigate greenhouse gas emissions has stimulated a renewed interest in nuclear energy worldwide. However, while numerous countries have shown interest in nuclear power over the course of history, many of them have not continued their pursuit and chosen to defer or abandon their peaceful nuclear power projects. Scrapping a national nuclear power program after making initial efforts implies significant challenges in such a course or a waste of national resources. Therefore, this study aims to identify the crucial factors that influence a country's decision to terminate or hold off its peaceful nuclear power programs. Our empirical analyses demonstrate that major nuclear accidents and leadership changes are significant factors that lead countries to terminate or defer their nuclear power programs. Additionally, we highlight that domestic politics (democracy), lack of military alliance with major nuclear suppliers, low electricity demand, and national energy security environments (energy import, crude oil price) can hamper a country's possibility of regaining interest in a nuclear power program after it has been scrapped, suspended, or deferred. The findings of this study have significant implications for policymakers and stakeholders in the energy sector as they strive to balance the competing demands of energy security, and environmental sustainability.

전 비상전원 적용을 위한 리튬계열전지 용량 설계 (Battery Sizing of Lithium-Based Battery for Emergency Power Supply in Nuclear Power Plants)

  • 박성윤;김건우;이평연;김종훈;박성백;김영미
    • 전력전자학회논문지
    • /
    • 제24권5호
    • /
    • pp.342-348
    • /
    • 2019
  • The emergency power supplies (EPSs) are required to increase battery sizing for protecting power source loss above designed criteria. This study proposes a sizing method for lithium-based batteries for EPSs in nuclear power plants on the basis of the calculation method for the required energy under variable conditions. The variable conditions are related with the characteristics of lithium-based batteries, such as the temperature of the location of EPS installation, aging, and design margin. The usage of lithium-based battery reduces the cost and installation space and enables the safe and long-term supply of power compared with the use of lead-acid battery.

Determinants of nuclear power expansion in Indonesia

  • Cho, Inkyung;Oh, Surim;Kim, Soohyeon;Ardin, Fadolly;Heo, Eunnyeong
    • Nuclear Engineering and Technology
    • /
    • 제53권1호
    • /
    • pp.314-321
    • /
    • 2021
  • As Indonesia is rich in natural resources, nuclear power remains a low priority among energy alternatives. However, Indonesia needs to introduce nuclear power to improve the atmospheric environment and to support sustainable economic growth. This study conducted a two-stage survey of logit-probit and analytic hierarchy process to analyze the perception of Indonesian energy policymakers regarding the introduction of nuclear power, the potential for change, and key decision factors. The analysis confirms that the perception of nuclear power is positive and that the willingness to expand nuclear power can improve if negative conditions, such as underdeveloped technology level, foreign aid and assistance, and safety issues are addressed. In addition, it is confirmed that the policy makers consider political/social and environmental factors to be more important for decision-making. The results of this study can give inplications and be used as a key reference for Indonesia's nuclear power policy

RADIATION SHIELDING EVALUATION OF IP-2 PACKAGES FOR LOW- AND INTERMEDIATE-LEVEL RADIOACTIVE WASTE

  • Kim, Min-Chul;Choi, Jong-Rak;Chung, Sung-Hwan;Ko, Jae-Hoon
    • Nuclear Engineering and Technology
    • /
    • 제40권6호
    • /
    • pp.511-516
    • /
    • 2008
  • Korea Hydro & Nuclear Power Co., Ltd. (KHNP) developed new IP-2 packages to transport low- and intermediate-level radioactive waste (LILW) steel drums from nuclear power plants to a disposal facility in accordance with IAEA and Korean transport regulations of radioactive material. Radiation shielding evaluation of the packages was carried out to demonstrate compliance with the regulatory requirements for IP-2 packages of radioactive material. Dose rate limits of LILW drums contained in the packages were determined.

Hybrid medium model for conjugate heat transfer modeling in the core of sodium-cooled fast reactor

  • Wang, X.A.;Zhang, Dalin;Wang, Mingjun;Song, Ping;Wang, Shibao;Liang, Yu;Zhang, Yapei;Tian, Wenxi;Qiu, Suizheng;Su, G.H.
    • Nuclear Engineering and Technology
    • /
    • 제52권4호
    • /
    • pp.708-720
    • /
    • 2020
  • Core-wide temperature distribution in sodium-cooled fast reactor plays a key role in its decay heat removal process, however the prediction for temperature distribution is quite complex due to the conjugate heat transfer between the assembly flow and the inter-wrapper flow. Hybrid medium model has been proposed for conjugate heat transfer modeling in the core. The core is modeled with a Realistic modeled inter-wrapper flow and hybrid medium modeled assembly flow. To validate present model, simulations for a three-assembly model were performed with Realistic modeling, traditional porous medium model and hybrid medium model, respectively. The influences of Uniform/Non-Uniform power distribution among assemblies and the Peclet number within the assembly flow have been considered. Compared to traditional porous medium model, present model shows a better agreement with in Realistic modeling prediction of the temperature distribution and the radial heat transfer between the inter-wrapper flow and the assembly flow.

A Study on Recalculating Nuclear Energy Generation Cost Considering Several External Costs

  • Kim, Hyun-Jung;Yee, Eric
    • 동력기계공학회지
    • /
    • 제22권6호
    • /
    • pp.5-10
    • /
    • 2018
  • Nuclear energy issues such as safety and social acceptance can not only influence the production costs of generating nuclear power, but also the external costs that are not reflected in market prices. Consequently, the social issues affiliated with nuclear power, beyond a severe accident, require some form of financial expense. The external social issues considered here are accident risk and realization, regulatory costs, and nuclear energy policy costs. Through several calculations and analyses of these external costs for nuclear power generation, it is concluded that these costs range from 7 to 27 \/kWh. Considering external costs are required for making energy plans, it could have an influence on generation costs.

MGGC2.0: A preprocessing code for the multi-group cross section of the fast reactor with ultrafine group library

  • Kui Hu;Xubo Ma;Teng Zhang;Xuan Ma;Zifeng Huang;Yixue Chen
    • Nuclear Engineering and Technology
    • /
    • 제55권8호
    • /
    • pp.2785-2796
    • /
    • 2023
  • How to generate the precise broad group cross section is important for the fast reactor design. In this study, a fast reactor multi-group cross-section generation code MGGC2.0 are developed in-house for processing ultrafine group MATXS format library. Validation and verification are performed for MGGC2.0 code by applying the benchmarks of ICSBEP handbook, and the results of MGGC2.0 agree well with that of MCNP. The consistent PN method with critical buckling search is in good agreement that condensed with TWODANT flux and flux moment for the inner core and outer core region. For the radial blanket and reflector, two region approximation method has been applied in MGGC2.0 by using collision Probability Method neutron flux solver. The RBEC-M benchmark was used to verify the power distribution calculation, and the relative error of power distribution comparison with the reference are less than 0.8% in the fuel region and the maximum relative error is 5.58% in the reflector region. Therefore, the precise broad cross section can be generated by MGGC2.0 for fast reactor.