Výsledky vyhledávání - "Kulesza Joel"

Akademický článek

A quantified approach to assessing the effectiveness of nuclear reactor pressure vessel neutron fluence monitoring programs

Autor: Kulesza Joel, Fischer Greg

Publikováno v: EPJ Web of Conferences, Vol 308, p 03004 (2024)

This paper presents a quantitative approach to characterize the effectiveness of neutron fluence monitoring programs using adjoint neutron transport calculations. The results of adjoint calculations are useful for this purpose because the adjoint sol

Externí odkaz: https://doaj.org/article/bf7930f580104d0bb163c3c280e2215a

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Akademický článek

Direct Sampling of Monte Carlo Flight Paths in Tetrahedral Meshes with Linear Finite-Element Cross Sections

Autor: Vaquer Pablo, Rising Michael, Kulesza Joel, Weaver Colin

Publikováno v: EPJ Web of Conferences, Vol 302, p 04008 (2024)

This paper describes how to directly sample Monte Carlo flight paths to simulate particle transport in media with continuously varying cross sections without using iterative methods. Specifically, this approach supports linear finite-element cross se

Externí odkaz: https://doaj.org/article/a79023a72fda4715877c91920b9376db

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Akademický článek

Lifetime Neutron Fluence Analysis of the Ringhals Unit 1 Boiling Water Reactor

Autor: Kulesza Joel A., Roudén Jenny, Green Eva-Lena

Publikováno v: EPJ Web of Conferences, Vol 106, p 02003 (2016)

This paper describes a neutron fluence assessment considering the entire commercial operating history (35 cycles or ∼ 25 effective full power years) of the Ringhals Unit 1 reactor pressure vessel beltline region. In this assessment, neutron (E >1.0

Externí odkaz: https://doaj.org/article/1f4343e59b834c809d9b3bf61afdfb0a

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Akademický článek

Comparison of Standard Light Water Reactor Cross-Section Libraries using the United States Nuclear Regulatory Commission Boiling Water Reactor Benchmark Problem

Autor: Kulesza Joel A., Alpan F. Arzu

Publikováno v: EPJ Web of Conferences, Vol 106, p 04006 (2016)

This paper describes a comparison of contemporary and historical light water reactor shielding and pressure vessel dosimetry cross-section libraries for a boiling water reactor calculational benchmark problem. The calculational benchmark problem was

Externí odkaz: https://doaj.org/article/06172ba49f924dc68b6196b28bd44697

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Akademický článek

Overview of the Consortium for the Advanced Simulation of Light Water Reactors (CASL)

Autor: Kulesza Joel A., Franceschini Fausto, Evans Thomas M., Gehin Jess C.

Publikováno v: EPJ Web of Conferences, Vol 106, p 03002 (2016)

The Consortium for Advanced Simulation of Light Water Reactors (CASL) was established in July 2010 for the purpose of providing advanced modeling and simulation solutions for commercial nuclear reactors. The primary goal is to provide coupled, higher

Externí odkaz: https://doaj.org/article/bfa8d7146a674189888274fb670a7731

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Akademický článek

Comparison of Standard Light Water Reactor Cross-Section Libraries using the United States Nuclear Regulatory Commission Pressurized Water Reactor Standard Core Loading Benchmark Problem

Autor: Alpan F. Arzu, Kulesza Joel A.

Publikováno v: EPJ Web of Conferences, Vol 106, p 04005 (2016)

This paper compares contemporary and historical light water reactor shielding and pressure vessel dosimetry cross-section libraries for a pressurized water reactor calculational benchmark problem with a standard out-in core loading. The calculational

Externí odkaz: https://doaj.org/article/932edd9e16f746beb52cb60328e501bb

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