Title:
PASSIVE SYSTEM WITH INCREASED RELIABILITY FOR DECAY-HEAT REMOVAL FROM A NUCLEAR REACTOR AND METHOD CARRIED OUT ON THE SYSTEM
Document Type and Number:
WIPO Patent Application WO/2022/122057
Kind Code:
A1
Abstract:
Passive system with increased reliability for decay-heat removal from nuclear reactor comprising heat exchanger (11), chimney (12) formed by two-channel pipe, and flow-redirection device (2) with inner channel (21) equipped with valve separating segment of channel (21) adjacent to reactor from segment of channel (21) adjacent to heat exchanger (11) and outer channel (22) equipped with at least one valve in partition separating segment of channel (22) adjacent to reactor from segment of channel (22) adjacent to heat exchanger (11), wherein segment of channel (21) adjacent to heat exchanger (11) is connected to segment of channel (22) adjacent to reactor by at least one connecting channel and segment of channel (22) adjacent to heat exchanger (11) is connected to segment of channel (21) adjacent to reactor by at least one connecting channel, wherein each of connecting channels is equipped with at least one valve.
Inventors:
HAJEK PETR (CZ)
Application Number:
PCT/CZ2021/050112
Publication Date:
June 16, 2022
Filing Date:
October 14, 2021
Export Citation:
Assignee:
UJV REZ A S (CZ)
International Classes:
G21C1/07; F16K1/00; G21C15/18
Foreign References:
| CZ306907B6 | 2017-09-06 | |||
| US4382908A | 1983-05-10 | |||
| CZ306907B6 | 2017-09-06 |
Other References:
POPE M A ET AL: "Thermal hydraulic challenges of Gas Cooled Fast Reactors with passive safety features", NUCLEAR ENGINEERING AND DESIGN, AMSTERDAM, NL, vol. 239, no. 5, 1 May 2009 (2009-05-01), pages 840 - 854, XP026064436, ISSN: 0029-5493, [retrieved on 20090402], DOI: 10.1016/J.NUCENGDES.2008.10.023
ZHENG Y ET AL: "Thermohydraulic transient studies of the Chinese 200MWe HTR-PM for loss of forced cooling accidents", ANNALS OF NUCLEAR ENERGY, PERGAMON PRESS, OXFORD, GB, vol. 36, no. 6, 1 June 2009 (2009-06-01), pages 742 - 751, XP026098284, ISSN: 0306-4549, [retrieved on 20090508], DOI: 10.1016/J.ANUCENE.2009.02.007
DUMAZ ET AL: "Gas-cooled fast reactors-Status of CEA preliminary design studies", NUCLEAR ENGINEERING AND DESIGN, AMSTERDAM, NL, vol. 237, no. 15-17, 31 July 2007 (2007-07-31), pages 1618 - 1627, XP022182499, ISSN: 0029-5493, DOI: 10.1016/J.NUCENGDES.2007.03.018
MAYER GUSZTÁV ED - SINGH RAM KUMAR ET AL: "Hot duct break transient with two- and three-loop ALLEGRO models", NUCLEAR ENGINEERING AND DESIGN, AMSTERDAM, NL, vol. 370, 5 November 2020 (2020-11-05), XP086385879, ISSN: 0029-5493, [retrieved on 20201105], DOI: 10.1016/J.NUCENGDES.2020.110911
STUDER ET AL: "CAST3M/ARCTURUS: A coupled heat transfer CFD code for thermal-hydraulic analyzes of gas cooled reactors", NUCLEAR ENGINEERING AND DESIGN, AMSTERDAM, NL, vol. 237, no. 15-17, 31 July 2007 (2007-07-31), pages 1814 - 1828, XP022182516, ISSN: 0029-5493, DOI: 10.1016/J.NUCENGDES.2007.03.016
EPINEY A ET AL: "Heavy-gas injection in the Generation IV gas-cooled fast reactor for improved decay heat removal under depressurized conditions", NUCLEAR ENGINEERING AND DESIGN, AMSTERDAM, NL, vol. 240, no. 10, 1 October 2010 (2010-10-01), pages 3115 - 3125, XP027355831, ISSN: 0029-5493, [retrieved on 20100928]
DUMAZ P. ET AL., NUCL. ENG. DES., vol. 237, 2007, pages 1618 - 1627
ZHENG Y ET AL: "Thermohydraulic transient studies of the Chinese 200MWe HTR-PM for loss of forced cooling accidents", ANNALS OF NUCLEAR ENERGY, PERGAMON PRESS, OXFORD, GB, vol. 36, no. 6, 1 June 2009 (2009-06-01), pages 742 - 751, XP026098284, ISSN: 0306-4549, [retrieved on 20090508], DOI: 10.1016/J.ANUCENE.2009.02.007
DUMAZ ET AL: "Gas-cooled fast reactors-Status of CEA preliminary design studies", NUCLEAR ENGINEERING AND DESIGN, AMSTERDAM, NL, vol. 237, no. 15-17, 31 July 2007 (2007-07-31), pages 1618 - 1627, XP022182499, ISSN: 0029-5493, DOI: 10.1016/J.NUCENGDES.2007.03.018
MAYER GUSZTÁV ED - SINGH RAM KUMAR ET AL: "Hot duct break transient with two- and three-loop ALLEGRO models", NUCLEAR ENGINEERING AND DESIGN, AMSTERDAM, NL, vol. 370, 5 November 2020 (2020-11-05), XP086385879, ISSN: 0029-5493, [retrieved on 20201105], DOI: 10.1016/J.NUCENGDES.2020.110911
STUDER ET AL: "CAST3M/ARCTURUS: A coupled heat transfer CFD code for thermal-hydraulic analyzes of gas cooled reactors", NUCLEAR ENGINEERING AND DESIGN, AMSTERDAM, NL, vol. 237, no. 15-17, 31 July 2007 (2007-07-31), pages 1814 - 1828, XP022182516, ISSN: 0029-5493, DOI: 10.1016/J.NUCENGDES.2007.03.016
EPINEY A ET AL: "Heavy-gas injection in the Generation IV gas-cooled fast reactor for improved decay heat removal under depressurized conditions", NUCLEAR ENGINEERING AND DESIGN, AMSTERDAM, NL, vol. 240, no. 10, 1 October 2010 (2010-10-01), pages 3115 - 3125, XP027355831, ISSN: 0029-5493, [retrieved on 20100928]
DUMAZ P. ET AL., NUCL. ENG. DES., vol. 237, 2007, pages 1618 - 1627
Attorney, Agent or Firm:
MACHU, Matej (CZ)
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