Thermal hydraulic analysis of a passively controlled DHR system

被引：22

作者：

Caramello, M. ^{[1
,2
]}

Gregorini, M. ^{[2
]}

Bertani, C. ^{[1
]}

De Salve, M. ^{[1
]}

Alemberti, A. ^{[2
]}

Panella, B. ^{[1
]}

机构：

[1] Politecn Torino, Dept Energy, Corso Duca Abruzzi 24, I-10129 Turin, Italy

[2] Ansaldo Nucl SpA, Corso FM Perrone 25, I-16161 Genoa, Italy

来源：

PROGRESS IN NUCLEAR ENERGY | 2017年 / 99卷

关键词：

Passive safety system control; ALFRED; Fast reactor; Relap5; Thermalhydraulics; Liquid metals; FAST-REACTOR; RELIABILITY-ANALYSIS; NONCONDENSABLE GAS; CONCEPTUAL DESIGN; COOLED REACTOR; HEAT REMOVAL; CONDENSER; CODE;

D O I：

10.1016/j.pnucene.2017.05.015

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

The safe operation of nuclear reactors cooled by liquid metal is an important issue to be addressed for the development of nuclear technology and presents specific aspects related to the properties of the coolant. While the main parameters influencing safety for water-cooled reactors are reasonably well known, DHR systems for reactors cooled by liquid metal present additional challenges related to coolant freezing, since solidification temperature is higher than the temperature of the final heat sink. If the primary coolant solidifies obstructions of the primary flow path can occur, inhibiting natural circulation and core cooling. This paper presents an innovative passive safety system for decay heat removal which passively delays the coolant freezing. The system adopts noncondensable gases to passively control the power removed from the primary system and to delay freezing in the long term while keeping primary system temperatures below an acceptable limit. The system is simulated by means of the Relap5-3D computer code for a loss of offsite power of the innovative lead-cooled reactor ALFRED. A sensitivity analysis has been carried out in order to study the effect of noncondensable gas pressure on the performance of the passive decay heat removal system, and in particular on the primary coolant temperatures. (C) 2017 Elsevier Ltd. All rights reserved.

引用

页码：127 / 139

页数：13

共 36 条

[1]

Akaki H, 1995, J NUCL SCI TECHNOL, V32, P517

[2]

Alemberti A., 2015, WO, Patent No. [2015/059672, 2015059672]

[3]

Alemberti A., 2013, INT C FAST REACT REL

[4]

[Anonymous], 2009, TECDOC1624 IAEA

[5]

[Anonymous], 2014, TECDOC1752 IAEA

[6]

Bandini Giacomino, 2008, SCI TECHNOL NUCL INS, V8

[7] Assessment of the enhanced DHRS configuration for MYRRHA reactor [J].

Bubelis, E. ;

Jaeger, W. ;

Bandini, G. ;

Alemberti, A. ;

Palmero, M. .

NUCLEAR ENGINEERING AND DESIGN, 2016, 307 :181-187

[8] Passive system reliability analysis: A study on the isolation condenser [J].

Burgazzi, L .

NUCLEAR TECHNOLOGY, 2002, 139 (01) :3-9

[9]

Caramello M, 2015, ICAPP INT C ADV NUCL, P838

[10] Design of cooler condensers for mixtures of vapors with noncondensing gases [J].

Colburn, AP ;

Hougen, OA .

INDUSTRIAL AND ENGINEERING CHEMISTRY, 1934, 26 :1178-1182

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