Topical sessions and contributions

Nuclear fuel cycle scenario studies - 1

Chair: Bo Feng (ANL, USA)

Introduction

Presentation of the fuel cycle related activities in the new European project PUMMA Francisco ALVAREZ VELARDE (CIEMAT, Spain)

Pu multi-recycling scenarios towards a PWR fleet for a stabilization of spent fuels inventories in France – Camille LAGUERRE (CEA, France)

Modeling Material Requirements of the Transition to HALEU Fueled Reactors - Amanda BACHMANN (University of Illinois, USA)

Nuclear fuel cycle scenario studies - 2

Chair: Guillaume MARTIN (CEA, France)

Scenario study of optimization of disposal method to reduce the amount of waste and disposal area in MOX fuel use – Eriko MINARI (Tokyo Institute of Technology, Japan)

Estimation of the vitrified canister production for a PWR fleet with the CLASS code - Léa TILLARD (ORANO, France)

A Scenario Study on Transition to the Closed Nuclear Fuel Cycle Using the Nuclear Energy System Modelling Application Package NESAPP – Andrei ANDRIANOV (MEPhl, Russia)

Fuel cycle simulation tool and physics models - 1

Chair: Xavier DOLIGEZ (CNRS, France)

Introduction

Development of nuclear fuel cycle scenario code NMB4.0 for integral analysis from front to back end of nuclear fuel cycle - Tomohiro OKAMURA (Tokyo Institute of Technology, Japan)

Simulation and validation of different nuclear fleets at equilibrium - Heddy BARALE (CEA, France)

The CORAIL-A option for recycling plutonium in PWR: overview of the latest investigations at Framatome - Barbara VEZZONI (Framatome, France)

Coupling fast reactor design and scenario calculations: a new methodology applied to scenario optimization - Kévin TIREL (CEA, France)

Fuel cycle simulation tool and physics models - 2

Chair: Paul Wilson (UW-Madison, USA)

Development of a MOX equivalence Python code package for ANICCA - Bart Vermeeren (Tractebel, Belgium)

Molten Salt Sourdough Full Core Application - Alexander Wheeler (University of Tennessee, USA)

IAEA's nuclear fuel cycle simulation tool- NFCSS and recent improvements - Kailash Agarwal (IAEA)

Development progress and methodology of FANCSEE fuel cycle code - Blazej Chmielarz (KTH, Sweden)

Nuclear fuel cycle interaction with electrical and energy systems - 1

Chair: Nicolas THIOLLIERE (IMT Atlantique, France)

Introduction

Electric transition in a fictitious emerging country - Impact of external constraints. - Sibylle MARTIN-LAUZER (CEA, France)

First approach to the estimation of Levelized cost of Electricity in ANICCA code - Ivan MERINO (Universidad Catolica Del Maule, Chili)

Impact of Fuel Supply Chain Disruptions on Energy Resilience: A case for Nuclear Energy Guillaume L’HER (Colorado School of Mines, USA)

Nuclear fuel cycle interaction with electrical and energy systems - 2

Chair: Adrien BIDAUD (Univesité de Grenoble, France)

Introduction

Adaptations of a current nuclear reactor towards more flexibility in order to accommodate a power system with a high insertion of variable renewable energy sources - Anne-Laure Mazauric (CEA, France)

Small Modular Reactor based solutions to enhance the grid reliability: identification of relevant criteria and preliminary assessment – Charly Boudot (CEA, France)

A new PoweR histOry generaTor tOol (PROTO) for French nuclear power stations at IRSN - Miguel Macias (IRSN, France)

Nuclear scenarios exploratory analysis - 1 

Chair: Francisco Alvarez Velarde (CIEMAT, Spain)

Introduction

Impact of disruption between options of plutonium multi-recycling: in PWRs and in SFRs - Jiali LIANG (CNRS, France)

Fuel cycle observables comparison from a UOX+MOX scenario based on irradiation libraries computed with different energy deposition models – Augusto Hernandez Solis (SCK, Belgium)

Uncertainty and optimization: a coupled problem for scenario analyses - Aris V. Skarbeli (CIEMAT, Spain)

Nuclear scenarios exploratory analysis - 2

Chair: Barbara VEZZONI (Framatome, France)

Introduction

Fuel Cycle Simulators for Nuclear Archaeology - Max Schalz (RWTH Aachen University, Germany)

DONJON5/CLASS coupled simulations of MOX/UO2 heterogeneous PWR core - Maxime Paradis (Polytechnique Montréal, Canada)

Application of Sensitivity Analysis in DYMOND/Dakota to Fuel Cycle Transition Scenarios - Scott Richards (ANL, USA)

 

 

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