Modeling of decay heat removal from CONSTOR RBMK-1500 casks during long-term storage of spent nuclear fuel

被引：15

作者：

Poskas, R. ^{[1
,2
]}

Simonis, V. ^{[1
]}

Jouhara, H. ^{[3
]}

Poskas, P. ^{[1
]}

机构：

[1] Lithuanian Energy Inst, Nucl Engn Lab, 3 Breslaujos, LT-44403 Kaunas, Lithuania

[2] Kaunas Univ Technol, Fac Mech Engn & Design, Dept Thermal & Nucl Energy, Studentu 56, LT-51424 Kaunas, Lithuania

[3] Brunel Univ London, Inst Energy Futures, Coll Engn Design & Phys Sci, Uxbridge UB8 3PH, Middx, England

来源：

ENERGY | 2019年 / 170卷

关键词：

RBMK-1500 spent nuclear fuel; Metal-concrete CONSTOR cask; Long-term storage; Thermal analysis; Local sensitivity analysis; THERMAL-ANALYSIS; CASTOR RBMK-1500; TEMPERATURE; DISPOSAL;

D O I：

10.1016/j.energy.2018.12.217

中图分类号：

O414.1 [热力学];

学科分类号：

摘要：

Management of spent nuclear fuel is a very important part in the whole cycle of nuclear energy generation. Ignalina nuclear power plant operated two RBMK-1500 reactors that are now being decommissioned. After careful consideration "dry" storage technology in casks was selected for the interim storage of spent nuclear fuel (SNF) for up to 50 years. SNF after pre-storage time in water pools for not less than 5 years is loaded into cast-iron or metal-concrete casks. In this paper decay heat removal was modelled from specific GNB (Gesellschaft fur Nuklear Behalter GmbH) metal-concrete (CONSTOR RBMK-1500) casks for the long-term storage period up to 300 years. The ALGOR code was used for the numerical modeling of the distribution of the heat fluxes and temperatures in a loaded cask placed in an open type storage facility in both summer and winter taking into account local environmental conditions. A local sensitivity analysis of the impact of fuel parameter uncertainties is also performed. (C) 2018 Elsevier Ltd. All rights reserved.

引用

页码：978 / 985

页数：8

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