Development of a decommissioning waste assessment module for heavy water reactors

被引：0

作者：

Shin, Hyun Young ^{[1
]}

Park, Kyu Tae ^{[1
]}

Park, Chan Hee ^{[1
]}

Kim, Sung Ryul ^{[1
]}

Oh, Jung Min ^{[1
]}

Lee, Ba Ro ^{[1
]}

Kim, Ji Ung ^{[1
]}

Kim, Hye Jin ^{[1
]}

Jeong, So Yun ^{[1
]}

Yoo, Wook Jae ^{[1
]}

机构：

[1] Orbitech Co., Ltd, 809, 1130, Beoman-ro, Geumcheon-gu, Seoul, Korea, Republic of

来源：

Annals of Nuclear Energy | 2025年 / 212卷

关键词：

Decommissioning (nuclear reactors) - Pressurized water reactors;

D O I：

10.1016/j.anucene.2024.111001

中图分类号：

学科分类号：

摘要：

In this study, we developed a Decommissioning Waste Assessment Module (DWAM) for Heavy Water Reactors (HWRs). To evaluate the waste amount of radioactive structures that make up a significant portion of decommissioning waste, we establish a comprehensive DB containing detailed information on the volume, weight, material type, and radioactivity of each decommissioning waste segment. Decommissioning waste assessment algorithms were developed and applied in the proposed module to optimize the calculated results, and their performance was evaluated to ensure accuracy and reliability. The DWAM currently being developed for the Wolsong Unit 1 commercial pressurized heavy water reactor is a technology that has the potential to be utilized not only for domestic reactors but also for reactors worldwide. In addition, the technology is expected to contribute to the development of technology related to the decommissioning of both radioactive and non-radioactive structures. © 2024 Elsevier Ltd

引用

共 50 条

[41] HIGH-SAFETY HEAVY-WATER REACTORS
VLADIMIRSKII, VV
ILICHEV, BI
KARAVAEV, GN
OKHLOPKOV, ML
SELIVERSTOV, VV
SOVIET ATOMIC ENERGY, 1989, 67 (05): : 787 - 794
[42] RECYCLING PLUTONIUM IN HEAVY-WATER POWER REACTORS
KHRISTEN.PI
JOURNAL OF NUCLEAR ENERGY, 1967, 21 (01): : 81 - &
[43] Construction management of Indian pressurized heavy water reactors
Bohra, SA
Sharma, PD
NUCLEAR ENGINEERING AND DESIGN, 2006, 236 (7-8) : 836 - 851
[44] A DECOUPLING ALGORITHM FOR LARGE PRESSURIZED HEAVY WATER REACTORS
Khan, Nafisah
Lu, Lixuan
NUCLEAR TECHNOLOGY, 2010, 172 (03) : 278 - 286
[45] Special section: Pressurized heavy water reactors safety
1600, American Society of Mechanical Engineers (ASME), United States (03):
[46] TRITIUM EXTRACTION FROM HEAVY WATER IN NUCLEAR REACTORS
LEGER, D
DIRIAN, G
ROTH, E
ENERGIE NUCLEAIRE PARIS, 1970, 12 (02): : 135 - &
[47] ADVANCED FUEL CYCLES IN HEAVY-WATER REACTORS
FOSTER, JS
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1977, 25 : 187 - 192
[48] MATCHING OF FUSION BREEDERS TO HEAVY-WATER REACTORS
LAVERGNE, G
ROBINSON, JE
MARTEL, JG
NUCLEAR TECHNOLOGY, 1975, 26 (01) : 12 - 22
[49] DEBATE ON HEAVY-WATER REACTORS RAISES STEAM
不详
ELECTRICAL REVIEW, 1976, 199 (20): : 16 - 17
[50] Computational estimate of tritium accumulation in heavy water reactors
Strakhov, E. B.
Vorob'ev, V. N.
Smirnov, O. A.
ATOMIC ENERGY, 2006, 100 (05) : 376 - 377

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