Final characterization of the first critical configuration for the TRIGA Mark II reactor of the University of Pavia using the Monte Carlo code MCNP

Alloni, D.; Tigliole, A. Borio di; Cammi, Antonio; Chiesa, D.; Clemenza, M.; Magrotti, Giovanni; Pattavina, L.; Pozzi, S.; Prata, Michele; Previtali, E.; Salvini, Andrea; Sartori, Alberto; Sisti, M.

doi:10.1016/j.pnucene.2014.02.022

Cited by 20 publications

(15 citation statements)

References 6 publications

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“…In order to describe accurately the reactor geometry and materials in the Serpent model, we exploit all the information that was collected in the previous years during the development of the TRIGA Mark II MCNP model [2,3]. These data are taken from the historical records stored at LENA and from the technical drawings of fuel elements and control rods that were provided by General Atomics.…”

Section: The Serpent Model Of the Triga Reactormentioning

confidence: 99%

“…The simulation results are presented in Fig. 2 [3] by propagating the uncertainties about fuel enrichment and nuclear graphite density. The standard deviation of the reactivity values from all simulations is equal to 0.10 $.…”

Section: Benchmark Analysis Of Low Power Reactormentioning

confidence: 99%

“…In the last years, the neutronics, the thermal-hydraulics and the fuel cycle of the TRIGA Mark II reactor of Pavia were analyzed and characterized in detail. Particularly, an MCNP [1] model of this reactor was developed to simulate the first criticality configuration at low power [2,3]. The MCNP neutronics calculations were then coupled to a thermal-hydraulic model to simulate the full power steady state [4].…”

Section: Introductionmentioning

confidence: 99%

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A new model with Serpent for the first criticality benchmarks of the TRIGA Mark II reactor

Castagna

Chiesa

Cammi

et al. 2018

Annals of Nuclear Energy

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We present a new model, developed with the Serpent Monte Carlo code, for neutronics simulation of the TRIGA Mark II reactor of Pavia (Italy). The complete 3D geometry of the reactor core is implemented with high accuracy and detail, exploiting all the available information about geometry and materials. The Serpent model of the reactor is validated in the fresh fuel configuration, through a benchmark analysis of the first criticality experiments and control rods calibrations. The accuracy of simulations in reproducing the reactivity difference between the low power (10 W) and full power (250 kW) reactor condition is also tested. Finally, a direct comparison between Serpent and MCNP simulations of the same reactor configurations is presented.

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Section: The Serpent Model Of the Triga Reactormentioning

confidence: 99%

Section: Benchmark Analysis Of Low Power Reactormentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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A new model with Serpent for the first criticality benchmarks of the TRIGA Mark II reactor

Castagna

Chiesa

Cammi

et al. 2018

Annals of Nuclear Energy

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“…Zirconium and its alloys are used to manufacture fuel claddings and guide tubes [9,34]. TRIGA fuels uniformly mix zirconium hydride (ZrH) and uranium [29,30,[35][36][37][38]. Zirconium offers an advantage of having neutron economies [39].…”

Section: Research Reactor Core Structure Materialsmentioning

confidence: 99%

Physical Ageing of The Research Reactor Core Structural Materials Due To Neutron Irradiation Exposure: A Review

Purba

2017

Jurnal Pengembangan Energi Nuklir

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PHYSICAL AGEING OF THE RESEARCH REACTOR CORE STRUCTURAL MATERIALS DUE TO NEUTRON IRRADIATION EXPOSURE: A REVIEW.A research reactor (RR) is a nuclear reactor that has function to generate and utilize neutron flux and radiation ionization for research purposes and industrial applications. More than 60% of current operating RRs have been operated for 30 years or more. As the time passes, the functional capabilities of structures, systems and components (SSCs) of those RRs deteriorate by physical ageing, which can be caused by neutron irradiation exposure such as irradiation induced dislocation and microstructural changes. To extend the lifetime and/or to avoid unplanned outages, ageing on the safety related SSCs of RRs need to be properly managed. An ageing management is a strategy to engineer, operate, maintenance, and control SSC degradation within acceptable limits. The purpose of this study is to review physical ageing of the core structural materials of the RRs caused by neutron irradiation exposure. In order to achieve this objective, a wide range of literatures are reviewed. Comprehensive discussions on irradiation behaviors are limited only on reactor vessel and core support structure materials made from zirconium and beryllium as well as their alloys, which are widely used in RRs. It is found that the stability of the mechanical properties of zirconium and beryllium as well as their alloys was mostly affected by the neutron fluences and temperatures. ABSTRAK PENUAAN MATERIAL STRUKTUR TERAS REAKTOR RISET SECARA FISIK YANG DISEBABKAN OLEH PAPARAN RADIASI NEUTRON: SEBUAH KAJIAN.Reaktor riset adalah reaktor nuklir yang difungsikan untuk pembangkitan dan pemanfaatan fluks neutron dan ionisasi radiasi untuk tujuan penelitian dan aplikasi industri. Lebih dari 60% reaktor riset yang ada saat ini telah beroperasi selama 30 tahun atau lebih. Seiring dengan berjalannya waktu, kemampuan struktur, sistem dan komponen (SSK) tentunya mengalami penurunan yang dikenal dengan penuaan fisik. Penuaan fisik ini dapat disebabkan oleh karena adanya paparan radiasi neutron seperti irradiasi yang menyebabkan terjadinya dislokasi dan perubahan mikrostruktur material. Untuk memperpanjang umur reaktor dan untuk mengurangi terjadinya pemadaman yang tidak diinginkan maka perlu dilakukan manajemen penuaan SSK, khususnya yang terkait dengan keselamatan operasi. Tujuan dari penelitian ini adalah untuk mengkaji penuaan fisik yang terjadi pada material struktur teras reaktor riset yang disebabkan oleh paparan iradiasi neutron. Untuk mencapai tujuan ini maka dilakukan kajian pada berbagai macam pustaka yang terkait. Pembahasan yang komprehensif tentang sifat-sifat iradiasi dibatasi hanya pada bejana reaktor dan material struktur pendukung teras yang terbuat dari zirconium dan beryllium dan senyawanya yang umum digunakan oleh reaktor riset. Dari kajian yang telah dilakukan, ditemukan bahwa stabilitas sifat-sifat mekanik zirconium dan beryllium serta senyawanya sangat dipengaruhi oleh fluent dan temperatur neutron. Kata kunci: Reaktor riset, p...

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“…Criticality calculations can be done using a variety of computer program such as MCNP-5 computer code, which is based on Monte Carlo method [1]. Critical analysis on various cases have been done by previous investigators, for example, on various geometry fuel arrangement by Doddy Kastanya [2], TRIGA Mark II reactor first criticality by D. Alloni et.al [3], as well as the fuel storage facility at the TRIGA Mark II research reactor by Loren R Metthew [4]. It also has been carried out for criticality calculation of high temperature reactors, research reactors and other criticality problems.…”

Section: Introductionmentioning

confidence: 99%

Criticality Analysis of Uranium Storage Facility With Formation Racks

Kuntjoro

2017

Tri Dasa Mega

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CRITICALITY ANALYSIS OF URANIUM STORAGE FACILITY WITH FORMATION RACKS.Uranium materials are needed for the uranium fuel production of research reactors and radioisotope. Before the uranium material is used, it is stored in the storage facility. One of the prerequisites for uranium material storage facilities is that it must be in the sub-critical condition. The purpose of this study is to analyze the criticality condition of uranium material storage facility located in PT. Inuki (Persero) and to ensure that the criticality condition is always in sub-critical state. Criticality analysis was performed using MCNP-5 program to determine the level of criticality of the three uranium material storage facilities at initial conditions and conditions after adding the storage racks. For analysing storage facilities 1 and 2, three scenarios of container on the storage rack formations were considered. Meanwhile, for analysing the storage facility 3, one scenario was considered. The results confirm that all strorages at initial condition and after adding storage racks formation were still in sub-critical condition (k-eff<1). These results are then used as the basis for the uranium materials management. It is also used as a basis for issuing an operational license by the nuclear energy regulatory body (BAPETEN).

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Final characterization of the first critical configuration for the TRIGA Mark II reactor of the University of Pavia using the Monte Carlo code MCNP

Cited by 20 publications

References 6 publications

A new model with Serpent for the first criticality benchmarks of the TRIGA Mark II reactor

A new model with Serpent for the first criticality benchmarks of the TRIGA Mark II reactor

Physical Ageing of The Research Reactor Core Structural Materials Due To Neutron Irradiation Exposure: A Review

Criticality Analysis of Uranium Storage Facility With Formation Racks

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