SCALE Analyses of Scenarios in the High-Temperature Gas-Cooled Reactor Fuel Cycle

Rabab Elzohery; Donny Hartanto; Rike Bostelmann; William Wieselquist

doi:10.2172/2455083

SCALE Analyses of Scenarios in the High-Temperature Gas-Cooled Reactor Fuel Cycle

Rabab Elzohery, Donny Hartanto, Rike Bostelmann, William Wieselquist

Research output: Book/Report › Commissioned report

Abstract

This report demonstrates the SCALE code system’s capabilities in modeling and simulating scenarios in the High-Temperature Gas-cooled Reactor (HTGR) nuclear fuel cycle as part of a United States Nuclear Regulatory Commission (NRC) project that aims to demonstrate the capabilities of the SCALE and MELCOR codes for non-light water reactor (non-LWR) modeling and simulation.

Original language	English
Place of Publication	United States
DOIs	https://doi.org/10.2172/2455083
State	Published - Oct 2024

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abstract = "This report demonstrates the SCALE code system{\textquoteright}s capabilities in modeling and simulating scenarios in the High-Temperature Gas-cooled Reactor (HTGR) nuclear fuel cycle as part of a United States Nuclear Regulatory Commission (NRC) project that aims to demonstrate the capabilities of the SCALE and MELCOR codes for non-light water reactor (non-LWR) modeling and simulation.",

author = "Rabab Elzohery and Donny Hartanto and Rike Bostelmann and William Wieselquist",

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AU - Elzohery, Rabab

AU - Hartanto, Donny

AU - Bostelmann, Rike

AU - Wieselquist, William

PY - 2024/10

Y1 - 2024/10

N2 - This report demonstrates the SCALE code system’s capabilities in modeling and simulating scenarios in the High-Temperature Gas-cooled Reactor (HTGR) nuclear fuel cycle as part of a United States Nuclear Regulatory Commission (NRC) project that aims to demonstrate the capabilities of the SCALE and MELCOR codes for non-light water reactor (non-LWR) modeling and simulation.

AB - This report demonstrates the SCALE code system’s capabilities in modeling and simulating scenarios in the High-Temperature Gas-cooled Reactor (HTGR) nuclear fuel cycle as part of a United States Nuclear Regulatory Commission (NRC) project that aims to demonstrate the capabilities of the SCALE and MELCOR codes for non-light water reactor (non-LWR) modeling and simulation.

U2 - 10.2172/2455083

DO - 10.2172/2455083

M3 - Commissioned report

BT - SCALE Analyses of Scenarios in the High-Temperature Gas-Cooled Reactor Fuel Cycle

CY - United States

ER -

SCALE Analyses of Scenarios in the High-Temperature Gas-Cooled Reactor Fuel Cycle

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