Alternative cores for a multipurpose experimental sodium-cooled fast reactor with U-ZR fuel

Tae Yang Noh; Myung Hyun Kim

Alternative cores for a multipurpose experimental sodium-cooled fast reactor with U-ZR fuel

Tae Yang Noh
, Myung Hyun Kim

Research output: Contribution to conference › Paper › peer-review

Abstract

The conceptual design of a Multipurpose Experimental Sodium cooled Fast Reactor (MESOF) based on U-Zr driver fuel was proposed at the previous study. Core performance characteristics and safety features are evaluated for alternative cores with U-TRU-Zr fuel and UO₂ fuel. All nuclear design calculations were done with TRANSX / DANTSYS / REBUS3(with DIF3D module) system, except effective delayed neutron fraction (β_eff) which was evaluated with MCNPX. The inherent safety feature is proven by negative sodium void worth for all cores. The shutdown margin of U-TRU-Zr core is enough to control large excess reactivity at BOC, but the safety feature for UO₂ core will be evaluated in later study.

Original language	English
Publication status	Published - 2014
Event	2014 International Conference on Physics of Reactors, PHYSOR 2014 - Kyoto, Japan Duration: 28 Sept 2014 → 3 Oct 2014

Conference

Conference	2014 International Conference on Physics of Reactors, PHYSOR 2014
Country/Territory	Japan
City	Kyoto
Period	28/09/14 → 3/10/14

Bibliographical note

Publisher Copyright:
© 2014 Westinghouse Electric Company LLC. All Rights Reserved.

Keywords

Experimental Fast Reactor
SFR
U-TRU-Zr
U-Zr
UO

Cite this

@conference{103d29c6ee654ebf8dea695ac58b59ca,

title = "Alternative cores for a multipurpose experimental sodium-cooled fast reactor with U-ZR fuel",

abstract = "The conceptual design of a Multipurpose Experimental Sodium cooled Fast Reactor (MESOF) based on U-Zr driver fuel was proposed at the previous study. Core performance characteristics and safety features are evaluated for alternative cores with U-TRU-Zr fuel and UO2 fuel. All nuclear design calculations were done with TRANSX / DANTSYS / REBUS3(with DIF3D module) system, except effective delayed neutron fraction (βeff) which was evaluated with MCNPX. The inherent safety feature is proven by negative sodium void worth for all cores. The shutdown margin of U-TRU-Zr core is enough to control large excess reactivity at BOC, but the safety feature for UO2 core will be evaluated in later study.",

keywords = "Experimental Fast Reactor, SFR, U-TRU-Zr, U-Zr, UO",

author = "Noh, \{Tae Yang\} and Kim, \{Myung Hyun\}",

note = "Publisher Copyright: {\textcopyright} 2014 Westinghouse Electric Company LLC. All Rights Reserved.; 2014 International Conference on Physics of Reactors, PHYSOR 2014 ; Conference date: 28-09-2014 Through 03-10-2014",

year = "2014",

language = "English",

}

TY - CONF

T1 - Alternative cores for a multipurpose experimental sodium-cooled fast reactor with U-ZR fuel

AU - Noh, Tae Yang

AU - Kim, Myung Hyun

PY - 2014

Y1 - 2014

N2 - The conceptual design of a Multipurpose Experimental Sodium cooled Fast Reactor (MESOF) based on U-Zr driver fuel was proposed at the previous study. Core performance characteristics and safety features are evaluated for alternative cores with U-TRU-Zr fuel and UO2 fuel. All nuclear design calculations were done with TRANSX / DANTSYS / REBUS3(with DIF3D module) system, except effective delayed neutron fraction (βeff) which was evaluated with MCNPX. The inherent safety feature is proven by negative sodium void worth for all cores. The shutdown margin of U-TRU-Zr core is enough to control large excess reactivity at BOC, but the safety feature for UO2 core will be evaluated in later study.

AB - The conceptual design of a Multipurpose Experimental Sodium cooled Fast Reactor (MESOF) based on U-Zr driver fuel was proposed at the previous study. Core performance characteristics and safety features are evaluated for alternative cores with U-TRU-Zr fuel and UO2 fuel. All nuclear design calculations were done with TRANSX / DANTSYS / REBUS3(with DIF3D module) system, except effective delayed neutron fraction (βeff) which was evaluated with MCNPX. The inherent safety feature is proven by negative sodium void worth for all cores. The shutdown margin of U-TRU-Zr core is enough to control large excess reactivity at BOC, but the safety feature for UO2 core will be evaluated in later study.

KW - Experimental Fast Reactor

KW - SFR

KW - U-TRU-Zr

KW - U-Zr

KW - UO

UR - https://www.scopus.com/pages/publications/85105327031

M3 - Paper

AN - SCOPUS:85105327031

T2 - 2014 International Conference on Physics of Reactors, PHYSOR 2014

Y2 - 28 September 2014 through 3 October 2014

ER -

Alternative cores for a multipurpose experimental sodium-cooled fast reactor with U-ZR fuel

Abstract

Conference

Bibliographical note

Keywords

Other files and links

Fingerprint

Cite this