Nuclear data target accuracy requirements for advanced reactors: The ALFRED case

Castelluccio, Donato Maurizio; Grasso, Giacomo; Lodi, Francesco; Peluso, V.; Mengoni, A.

doi:10.1016/j.anucene.2021.108533

Cited by 19 publications

(6 citation statements)

References 12 publications

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“…As a promising technology capable of meeting the Generation IV goals of Nuclear Power Plants (NPPs), ALFRED [55,56], a conceptual reactor design within the European nuclear community, has been the subject of various studies of reactor design [37,[57][58][59], control design [60,61], and reliability and risk analysis [62,63]. ALFRED is designed to operate in a flexible way [64][65][66] and is expected to reach operational conditions of an industrially deployable small modular lead fast reactor around the year 2035-2040 [55], making it a perfect candidate of NPPs to be considered for coping with the variability of RESs, within a load-following schedule.…”

Section: Case Studymentioning

confidence: 99%

A sequential decision problem formulation and deep reinforcement learning solution of the optimization of O&M of cyber-physical energy systems (CPESs) for reliable and safe power production and supply

Hao

Maio

Zio

2023

Reliability Engineering & System Safety

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Section: Case Studymentioning

confidence: 99%

A sequential decision problem formulation and deep reinforcement learning solution of the optimization of O&M of cyber-physical energy systems (CPESs) for reliable and safe power production and supply

Hao

Maio

Zio

2023

Reliability Engineering & System Safety

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“…A robust methodology to estimate the overestimation or underestimation of integral parameters to be the most limiting for them can be found in Ref. [9].…”

Section: Review Of Tarsmentioning

confidence: 99%

WPEC/SG46 Exercise on Target Accuracy Requirement

Cabellos,

Hursin,

Palmiotti

2023

EPJ Web of Conf.

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Recently, a second Target Accuracy Requirements (TAR) exercise is launched in the framework of the WPEC/S46 on “Efficient and Effective Use of Integral Experiments for Nuclear Data Validation”. The TAR exercise aims at quantifying nuclear data needs, in terms of uncertainty reduction, to meet target accuracies on specific integral parameters. These target accuracies are driven by reactor and fuel cycle design. The goal is to provide the NEA/HPRL with new requirements of “nuclear data uncertainty reduction”

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“…Because of the relatively large volume fractions of Lead in the FAs and reflector dummy assemblies, the sensitivity of several key integral parameters to the cross-sections of Lead isotopes is high. As reference, three Lead isotopes reactions are among the top-twelve contributors to the uncertainty of the multiplication factor [3], namely the inelastic cross-section of 207 Pb (by 84.4 pcm); the elastic cross-section of 208 Pb (by 77.6 pcm); the inelastic cross-section of 206 Pb (by 72.0 pcm).…”

Section: The Alfred Reactormentioning

confidence: 99%

“…The 80 energy group structure previously refined for ALFRED reactor studies [3] was chosen for this analysis in both systems. Then the GPT was applied to analyze at first the sensitivity of the selected observables to nuclear data for both reactors, and then also for the representativeness of the planned experiment in TAPIRO to the reference ALFRED case.…”

Section: Calculation Models and Codes Specificationsmentioning

confidence: 99%

Neutrons propagation in Lead: A feasibility study for experiments in the RSV TAPIRO fast research reactor

et al. 2023

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The increasing worldwide interest in Lead-cooled Fast Reactors (LFRs) substantiates the need to validate the analytical codes and methods used to support their design. For neutronic analyses, this is chiefly reflected in assessing the impact of nuclear data uncertainties on the integral and local parameters resulting from such analyses. The aim of refining nuclear data moves continuous efforts for more accurate measurements, be them differential or integral, for which adequate facilities are required. The availability at the ENEA's Casaccia research center of a fast source reactor – RSV TAPIRO – provides a unique opportunity to perform new integral experiments in support of fast reactors, including LFRs, owing to the well-characterized neutron spectrum of the thermal column. A series of experiments has been envisaged, dealing with the use of Lead in a reactor. The experiments concern the propagation of neutrons through blocks of materials representing relevant elements of a reactor core, and ranging from pure Lead to mixtures reproducing portions of the reflector and shield in LFRs. The paper is focused on the feasibility study of some of these experiments in which Lead and mixture blocks are inserted in the so-called thermal column of the RSV TAPIRO reactor and irradiated by the neutron flux emerging from the Copper reflector surrounding the reactor core.

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Nuclear data target accuracy requirements for advanced reactors: The ALFRED case

Cited by 19 publications

References 12 publications

A sequential decision problem formulation and deep reinforcement learning solution of the optimization of O&M of cyber-physical energy systems (CPESs) for reliable and safe power production and supply

A sequential decision problem formulation and deep reinforcement learning solution of the optimization of O&M of cyber-physical energy systems (CPESs) for reliable and safe power production and supply

WPEC/SG46 Exercise on Target Accuracy Requirement

Neutrons propagation in Lead: A feasibility study for experiments in the RSV TAPIRO fast research reactor

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