Accurate, high-resolution full core simulations of prismatic high temperature reactors for burnup and transient analysis remain a challenge. The cores are geometrically large, but some features are quite small (tristructural isotropic (TRISO) particles, burnable poison pellets). The treatment of both neutron scattering in graphite and resonance capture are complex and not adequately captured using the methods traditionally used in High Temperature Gas-cooled Reactors (HTGR) and commonly used in Light Water Reactors (LWR). For transient analysis, temperature feedback is a function of the TRISO fuel form, but full core models cannot resolve phenomena at this scale without averaging over space and energy. For burnup calculations, a second level of heterogeneity [1] must be resolved to capture the local effects of fuel and burnable poisons, while accurately propagating their effects through and between blocks. The HTGR Methods and Simulation group has been utilizing the INL-developed PHISICS/RELAP5-3D© (P/R) [2-3], code suite for participation in the Organization for Economic Cooperation and Development (OECD) Modular High Temperature Gas Cooled Reactor (MHTGR) Benchmark, funded by the US Department of Energy (DOE) under the Advanced Reactor Technologies (ART) program [4-5]. The MHTGR-350 benchmark consists of several lattice, steady-state and transient exercises, and the P/R code has been successfully applied to most of the cases defined [6-9]. In addition to this code-to-code verification activity, it is planned that P/R will be validated using data from several Loss of Forced Cooling (LOFC) tests performed at the High Temperature Test Reactor (HTTR) [10] in a joint effort with Japan Atomic Energy Agency (JAEA) under the Civil Nuclear Energy Working Group (CNWG) project. These verification and validation simulations will identify code and model discrepancies, sensitivities, and establish the current state-of-the-art in HTGR simulation. The Department of Astronautical, Electrical and Energy Engineering (DIAEE), “Sapienza” University has been involved in the development of P/R since 2014 through various graduate and PhD student projects [11-12]. In the framework of this collaboration the P/R optimization for application on the OECD MHTGR-350 and HTTR models will be carried out.

New phisics perturbation method module verification using the HTTR neutronic model / Balestra, Paolo; Alfonsi, Andrea; Strydom, Gerhard; Sen, Ramazan S.; Rabiti, Cristian; Giannetti, Fabio; Caruso, Gianfranco. - In: TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY. - ISSN 0003-018X. - 117:(2017), pp. 1412-1415. (Intervento presentato al convegno 2017 Transactions of the American Nuclear Society, ANS 2017 tenutosi a Marriott Wardman Park, usa).

New phisics perturbation method module verification using the HTTR neutronic model

Balestra, Paolo
;
Alfonsi, Andrea;Giannetti, Fabio;Caruso, Gianfranco
Supervision
2017

Abstract

Accurate, high-resolution full core simulations of prismatic high temperature reactors for burnup and transient analysis remain a challenge. The cores are geometrically large, but some features are quite small (tristructural isotropic (TRISO) particles, burnable poison pellets). The treatment of both neutron scattering in graphite and resonance capture are complex and not adequately captured using the methods traditionally used in High Temperature Gas-cooled Reactors (HTGR) and commonly used in Light Water Reactors (LWR). For transient analysis, temperature feedback is a function of the TRISO fuel form, but full core models cannot resolve phenomena at this scale without averaging over space and energy. For burnup calculations, a second level of heterogeneity [1] must be resolved to capture the local effects of fuel and burnable poisons, while accurately propagating their effects through and between blocks. The HTGR Methods and Simulation group has been utilizing the INL-developed PHISICS/RELAP5-3D© (P/R) [2-3], code suite for participation in the Organization for Economic Cooperation and Development (OECD) Modular High Temperature Gas Cooled Reactor (MHTGR) Benchmark, funded by the US Department of Energy (DOE) under the Advanced Reactor Technologies (ART) program [4-5]. The MHTGR-350 benchmark consists of several lattice, steady-state and transient exercises, and the P/R code has been successfully applied to most of the cases defined [6-9]. In addition to this code-to-code verification activity, it is planned that P/R will be validated using data from several Loss of Forced Cooling (LOFC) tests performed at the High Temperature Test Reactor (HTTR) [10] in a joint effort with Japan Atomic Energy Agency (JAEA) under the Civil Nuclear Energy Working Group (CNWG) project. These verification and validation simulations will identify code and model discrepancies, sensitivities, and establish the current state-of-the-art in HTGR simulation. The Department of Astronautical, Electrical and Energy Engineering (DIAEE), “Sapienza” University has been involved in the development of P/R since 2014 through various graduate and PhD student projects [11-12]. In the framework of this collaboration the P/R optimization for application on the OECD MHTGR-350 and HTTR models will be carried out.
2017
2017 Transactions of the American Nuclear Society, ANS 2017
nuclear energy and engineering; safety, risk, reliability and quality
04 Pubblicazione in atti di convegno::04c Atto di convegno in rivista
New phisics perturbation method module verification using the HTTR neutronic model / Balestra, Paolo; Alfonsi, Andrea; Strydom, Gerhard; Sen, Ramazan S.; Rabiti, Cristian; Giannetti, Fabio; Caruso, Gianfranco. - In: TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY. - ISSN 0003-018X. - 117:(2017), pp. 1412-1415. (Intervento presentato al convegno 2017 Transactions of the American Nuclear Society, ANS 2017 tenutosi a Marriott Wardman Park, usa).
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11573/1274699
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