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In case of a hypothetical severe accident in a Sodium-cooled Fast Reactor (SFR), coolability of the debris bed in the post-accident phase plays a vital role in mitigating the accident and ensuring the structural integrity of the reactor vessel. Few numerical studies are reported in literature, in which the boiling heat transfer in debris bed is expressed as equivalent heat conduction using similarity law between heat conduction and two-phase heat transfer. However, these studies assumed steady state mass conservation for the boiling zone and neglected the gravity force. Hence, a detailed study has been carried out for various particle sizes and porosities of SFR debris to investigate the influence of above considerations. The effect of gravity on debris bed coolability is studied using steady state model of Lipinski, which showed that gravity has a non-negligible effect, for particle size of 0.3 mm and porosity of 0.5. However, the gravitation force was found to have a negligible effect in dryout heat flux estimation for the bottom cooled configuration. A transient numerical model is developed for simulating the boiling phenomena in debris beds and validated with the published experimental results. The assumption of steady state mass conservation is verified by carrying out transient analysis, which indicated early prediction of the dryout inception. For time dependent heat generation case, the unsteady mass conservation predicted higher DHF compared to constant heat generation.

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권호기사 목록 테이블로 기사명, 저자명, 페이지, 원문, 기사목차 순으로 되어있습니다.
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Extended cognitive reliability and error analysis method for advanced control rooms of nuclear power plants Xiaodan Zhang, Shengyuan Yan, Xin Liu p. 3472-3482

Real-time measurements and modeling of sodium combustion aerosol dynamics in test chamber to improve the evaluation of SFR containment aerosol behaviour Usha Pujala, Amit Kumar, Subramanian Venkatesan, Sujatha Pavan Narayanam, Venkatraman Balasubramanian p. 3483-3490

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Titanium alloys : a closer-look at mechanical, gamma-ray, neutron, and transmission properties of different grade alloys through MCNPcode application Ghada ALMisned, Omer Guler, Duygu Sen Baykal, G. Kilic, H.O. Tekin p. 3501-3511

(An) efficient numerical modeling approach for coupled electrical cabinets in nuclear power plants Sudeep Das Turja, Md. Rajibul Islam, Dong Van Nguyen, Dookie Kim p. 3512-3527

Effects of microalloying element addition on mechanical properties of SA508 Gr.1A low-alloy steels Se-mi Hyun, Min-Chul Kim, Seokmin Hong, Jongmin Kim, Seok Su Sohn p. 3528-3535

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Monte Carlo simulation and optimization of neutron ray shielding performance of related materials Tongyan Cui, Faquan Wang, Linhan Bing, Rui Wang, Zhongjian Ma, Qingxiu Jia p. 3545-3552

Fission counter array for pulse-mode measurements of high-flux and high-energy neutrons Pilsoo Lee p. 3553-3557

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(A) new surrogate method for the neutron kinetics calculation of nuclear reactor core transients Xiaoqi Li, Youqi Zheng, Xianan Du, Bowen Xiao p. 3571-3584

Study on producing radioisotopes based on fission or radiative capture method in a high flux reactor Wei Xu, Jian Li, Lei Shi p. 3585-3593

Prediction of small-scale leak flow rate in LOCA situations using bidirectional GRU Hye Seon Jo, Sang Hyun Lee, Man Gyun Na p. 3594-3601

Method of the known cross sections for calibration of the fast neutron spectrometer with a single-crystal stilbene based detector I.V. Urupa, E.V. Ryabeva, R.F. Ibragimov, V.D. Sapozhnikov p. 3602-3607

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Noticeable localized corrosion of solid boric acid on 304 stainless steel Xinzhu Li, Wen Sun, Guiling Ning p. 3616-3625

Uncertainty quantification based on similarity analysis of reactor physics benchmark experiments for SFR using TRU metallic fuel YuGwon Jo, Jaewoon Yoo, Jong-Hyuk Won, Jae-Yong Lim p. 3626-3643

Conceptual design for a 5 kWe space nuclear reactor power system Huaping Mei, Dali Yu, Shengqin Ma, Jiansong Zhang, Yongju Sun, Chao Chen, Meisheng He, Haixia Wang, Yang Li, Liang Wang, Taosheng Li, Jie Yu p. 3644-3653

Solution of OECD/NEA PWR MOX/UO2 benchmark with a high-performance pin-by-pin core calculation code Hyunsik Hong, Jooil Yoon p. 3654-3667

Impact of fuel temperature on nuclear core design calculations Dušan Čalič, Luka Snoj, Marjan Kromar p. 3668-3685

ACE surrogate model-based uncertainty and sensitivity analysis methods for severe accident codes Kwang-Il Ahn p. 3686-3699

High fidelity core flow measurement experiment for an advanced research reactor using a real scale mockup Taeil Kim, Yohan Lee, Donkoan Hwang, WooHyun Jung, Nakjun Choi, Seong Seok Chung, Jihun Kim, Jonghark Park, Hyung Min Son, Kiwon Song, Huiyung Kim, HangJin Jo p. 3700-3716

Identification of primary input parameters affecting evacuation in ventilated main control room through CFAST simulations and application of a machine learning algorithm to replace CFAST model Sumit Kumar Singh, Jinsoo Bae, Yu Zhang, Saerin Lim, Jongkook Heo, Seoung Bum Kim, Weon Gyu Shin p. 3717-3729

Study on the cantilever ratio optimization of high-temperature molten salt pump for molten salt reactor based on structural integrity Xing-Chao Shen, Yuan Fu, Jian-Yu Zhang, Jin Yang, Zhi-Jun Li p. 3730-3739

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참고문헌 (17건) : 자료제공( 네이버학술정보 )

참고문헌 목록에 대한 테이블로 번호, 참고문헌, 국회도서관 소장유무로 구성되어 있습니다.
번호 참고문헌 국회도서관 소장유무
1 Particle Bed Heat Removal with Subcooled Sodium: D-4 Results and Analysis 미소장
2 The effect of channeling on the dryout of heated particulate beds immersed in a liquid pool 미소장
3 In-Reactor Experiments on the Cooling of Fast Reactor Debris 미소장
4 Pouring of 100-kg-Scale Molten UO2 into Sodium 미소장
5 Capillary Behavior in Porous Solids 미소장
6 On the measurement and mechanism of dryout in volumetrically heated coarse particle beds 미소장
7 Dryout heat flux experiments with deep heterogeneous particle bed 미소장
8 Fluid Flow through Randomly Packed Columns and Fluidized Beds 미소장
9 An improved model for two-phase flow through beds of coarse particles 미소장
10 On the Location and Mechanisms of Dryout in Top-Fed and Bottom-Fed Particulate Beds 미소장
11 Validation and application of the WABE code: Investigations of constitutive laws and 2D effects on debris coolability 미소장
12 PATH – An experimental facility for natural circulation heat transfer studies related to Post Accident Thermal Hydraulics 미소장
13 A hydrodynamic model for two-phase flow through porous media 미소장
14 A Coolability Model for Postaccident Nuclear Reactor Debris 미소장
15 Numerical Investigation of Dryout Heat Flux and Heat Transfer Characteristics in Core Debris Bed of SFR After Severe Accident 미소장
16 Study on high-speed calculation of debris bed coolability for sodium-cooled fast reactors 미소장
17 Model for boiling and dryout in particle beds 미소장

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