Computational analysis for predicting fission product release of PeLUIt-40 under normal operating conditions

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Anik Purwaningsih , Dwi Irwanto , Julwan H. Purba
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引用次数: 0

Abstract

PeLUIt (Pembangkit Listrik dan Uap untuk Industri) is an High Temperature Gas Cooled Reactor (HTGR)-based cogeneration reactor designed by the Indonesian National Nuclear Energy Agency of Indonesia (now the Research Organization for Nuclear Energy, BRIN). HTGR uses tri-structural isotropic (TRISO) coated particle fuel, which is the main barrier to the release of fission products. The ability of the fuel to retain fission products both under normal and accident conditions is very important for design licensing. This study was conducted to predict the release of fission products of PeLUIt-40 (PeLUIt with a power of 40 MWt) under normal operating conditions. In this study, the Source Term Analysis Code System (STACY) was used to predict the release of radiologically significant fission products Ag110m, Cs137, I131, and Sr90. OpenMC was used to calculate neutronic parameters such as burnup (Fissions per initial heavy metal atom—FIMA), fast neutron fluence, and fission product inventory. A single pebble model with different irradiation times and temperature variations was used to simulate the fission product release in PeLUIt-40. The time and temperature variations were used to investigate the sensitivity of the fission product release fraction in PeLUIt-40 fuel to these parameters and to estimate the maximum safe fuel temperature during operation. The simulation results showed that the largest release fraction was Ag110m release compared to other radionuclide releases. At the normal operating temperature of 977 °C, the fission product release fractions during one-through-one-out (OTTO) and 5-pass cycles were two orders of magnitude lower than the failure fraction for the high-temperature reactor (HTR)-Module 1.6x10-4 and there was no defective particle during operation. In the OTTO cycle, the maximum fuel temperature that did not cause defective particle was about 1250 °C, but the Ag110m release fraction exceeded 1.6x10-4. The release fraction of all fission products in the OTTO cycle is below 1.6x10-4 when the maximum fuel temperature is 1025 °C. While in the 5-pass cycle, the maximum fuel temperature of about 1200 °C does not cause defective particle, but the release fraction of Ag110m exceeds 1.6x10-4. The release fraction of all fission products in the 5-pass cycle is below 1.6x10-4 when the maximum fuel temperature is 1020°C. The simulation results confirm that the release of fission products in PeLUIt-40 fuel during normal operation is lower than the safety requirement limit of 1.6x10-4 and no defective particle occurs during normal operation. This indicates that the TRISO-coated PeLUIt-40 particles are able to prevent the release of fission products at normal operating temperatures.
预测 PeLUIt-40 在正常运行条件下裂变产物释放的计算分析
PeLUIt(Pembangkit Listrik dan Uap untuk Industri)是一种基于高温气冷堆(HTGR)的热电联产反应堆,由印度尼西亚国家核能机构(现为核能研究组织,BRIN)设计。高温气冷堆使用三结构各向同性(TRISO)涂层颗粒燃料,这是裂变产物释放的主要屏障。燃料在正常和事故条件下保留裂变产物的能力对于设计许可非常重要。本研究旨在预测 PeLUIt-40(功率为 40 兆瓦的 PeLUIt)在正常运行条件下的裂变产物释放情况。在这项研究中,使用源项分析代码系统 (STACY) 预测了具有放射性意义的裂变产物 Ag110m、Cs137、I131 和 Sr90 的释放。OpenMC 用于计算中子参数,如燃烧度(每个初始重金属原子的裂变量-FIMA)、快中子通量和裂变产物存量。使用不同辐照时间和温度变化的单一鹅卵石模型模拟 PeLUIt-40 中的裂变产物释放。利用时间和温度变化来研究 PeLUIt-40 燃料中裂变产物释放分数对这些参数的敏感性,并估算运行期间燃料的最高安全温度。模拟结果表明,与其他放射性核素释放量相比,Ag110m 的释放量最大。在 977 ℃ 的正常运行温度下,一穿一出(OTTO)循环和五通循环的裂变产物释放分数比高温堆(HTR)-模块的失效分数低两个数量级,为 1.6x10-4,运行期间没有出现缺陷粒子。在 OTTO 循环中,不产生缺陷粒子的最高燃料温度约为 1250 ℃,但 Ag110m 的释放分数超过了 1.6x10-4。当最高燃料温度为 1025 ℃ 时,OTTO 循环中所有裂变产物的释放分数都低于 1.6x10-4。而在 5 次循环中,最高燃料温度约为 1200 ℃ 时不会产生缺陷粒子,但 Ag110m 的释放分数超过了 1.6x10-4。当最高燃料温度为 1020 ℃ 时,5 次循环中所有裂变产物的释放分数都低于 1.6x10-4。模拟结果证实,在正常运行期间,PeLUIt-40 燃料中裂变产物的释放量低于 1.6x10-4 的安全要求限值,并且在正常运行期间不会出现缺陷粒子。这表明,TRISO 涂层 PeLUIt-40 颗粒能够防止在正常运行温度下释放裂变产物。
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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