Thorium fuel performance assessment in HTRs

Allelein, Hans-Josef; Kania, M.J.; Nabielek, H.; Verfondern, Karl

doi:10.1016/j.nucengdes.2013.11.027

Cited by 8 publications

(6 citation statements)

References 6 publications

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“…Early HTR technology actually ran on a mixture of thorium and highly‐enriched uranium. Later, most HTR systems switched to lowly‐enriched uranium after 1980 68 . The HTR can also support Th‐Pu fuel cycle to possibly burn Pu and actinide contents from spent nuclear fuels.…”

Section: Htrmentioning

confidence: 99%

Review of the microheterogeneous thoria‐urania fuel for micro‐sized high temperature reactors

2020

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Summary This paper presents a systematic review of the micro‐modular thorium‐fueled high temperature reactors (HTR) loaded with duplex fuel pellet design. Specifically, each unique criterion of the design is discussed separately in an attempt to understand the combined advantages of the proposed reactor. Micro modular HTRs have great potential as a source of electricity or industrial heat in the future. The use of thorium not only improves its economic performance and safety, but also prolongs its operation. Nevertheless, the traditional seed‐and‐blanket configuration would not be able to maximize the thorium fuel burnup. As such, a new tristructural‐isotopic (TRISO) fuel based on duplex pellet designs were proposed instead. It should be noted that these duplex pellets were not practical for pressurized water reactor (PWR) technology due to its uneven power distribution which possibly leads to a very high local pellet temperature. However, this unorthodox inherent characteristics of the duplex pellets may actually suit the HTR burnup profile better due to its substantially higher thermal margin ‐ thus possibly enabling a relatively long operation of the HTR. The paper shall thereby provide a reasonably sound justification for the detailed technical investigations of the proposed reactor design.

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Section: Htrmentioning

confidence: 99%

Review of the microheterogeneous thoria‐urania fuel for micro‐sized high temperature reactors

2020

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“…Reaktor RDE dirancang menggunakan bahan bakar kernel partikel berlapis (coated fuel particle) TRISO yang berbentuk bola (pebble) [5,6] . Dalam operasinya reaktor RDE dapat menggunakan bahan bakar kernel uranium dioksida (UO2) [7,8,9] , thorium oksida (ThO2/UO2) [10,11,12] maupun plutonium dioksida (PuO2) [13,14] tanpa merubah bentuk dan geometri teras reaktor. Pada penelitian ini pembahasan hanya dilakukan terhadap RDE yang menggunakan bahan bakar UO2 dengan pengkayaan 235 U sebesar 17 %.…”

Section: Reaktorunclassified

“…Nilai kuat sumber neutron reaktor RDE pada teras awal diperoleh dengan menggunakan persamaan (1) dan persamaan (2), serta nilai keluaran dari MCNP untuk jumlah rerata neutron diproduksi per fission ( ) yang terjadi sebesar 2,4410 neutron/fisi adalah: NSSRDE = 10 7 (watt) X 3.47x10 10 (fisi/watt.detik) X 2,4410 (neutron/fisi) = 8,47027x10 17 neutron/detik Untuk menentukan laju dosis neutron yang dihasilkan dari teras awal RDE dihitung dari fluks neutron rata-rata dalam teras awal RDE menggunakan persamaan Tabel 4. Faktor konversi fluks neutron ke dalam dosis neutron [19] Energi, E Dengan demikian dapat dikatakan bahwa desain ketebalan perisai biologis yang dimodelkan sudah mencukupi dan aman bagi pekerja radiasi, sehingga pekerja radiasi aman dan terlindungi dari sumber radiasi neutron.…”

Section: Hasil Dan Pembahasanunclassified

Analisis Kuat Sumber Neutron Dan Perhitungan Laju Dosis Neutron Teras Awal Rde

Suwoto

Adrial

Zuhair

2017

urania

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ABSTRAK ANALISIS KUAT SUMBER NEUTRON DAN PERHITUNGAN LAJU DOSIS NEUTRON TERAS AWAL RDE.Teras reaktor RDE (Reaktor Daya Eksperimental) berbentuk silinder non anular, berbahan bakar kernel partikel berlapis TRISO yang berbentuk bola (pebble) dan berpendingin gas helium. Desain teras reaktor ini sangat aman karena mengadopsi teknologi reaktor temperatur tinggi HTGR (High Temperature Gas-cooled Reactor) dengan keselamatan inheren pasif. Temperatur keluaran gas helium teras reaktor dirancang pada kisaran 700 C dengan temperatur masukan sekitar 250 C. Di samping menghasilkan listrik, reaktor didisain menghasilkan panas temperatur tinggi yang dapat digunakan untuk keperluan kogenerasi lainnya (penelitian panas proses lainnya). Bahan bakar reaktor berbentuk bola yang berisikan kernel partikel berlapis TRISO yang berupa uranium dioksida (UO2) berpengkayaan 17 % ( 235 U). Lapisan TRISO terdiri 4 lapisan yaitu lapisan karbon penyangga berpori, lapisan karbon pirolitik bagian dalam (IPyC, Inner Pyrolitic Carbon), lapisan Silikon Karbida (SiC) dan lapisan pirolitik karbon bagian luar (OPyC, Outer Pyrolitic Carbon). Analisis kuat sumber dan perhitungan awal laju dosis neutron pada RDE dilakukan menggunakan program Monte Carlo MCNP5v1.2. Pemodelan heterogenitas ganda bahan bakar dilakukan pada bahan bakar kernel partikel berlapis TRISO dan pada bahan bakar bola pada teras reaktor. Pemanfaatan program EGS99304 untuk menentukan jumlah struktur group energi yaitu 640 (SAND-II group structure) yang digunakan dalam perhitungan spektrum neutron pada reaktor. Teras reaktor dibagi dalam 100 zona (10 arah radial dan 10 arah aksial). Analisis hasil perhitungan menunjukkan bahwa kuat sumber neutron reaktor sebesar 8,47027X10 17 neutron/detik. Distribusi laju dosis neutron ditentukan menggunakan faktor konversi fluks neutron ke dalam dosis neutron dari International Commission on Radiological Protection (ICRP) dan National Council on Radiation Protection and Measu-rements (NCRP). Hasil perhitungan awal laju dosis neutron dengan faktor konversi ICRP-21 dan NCRP-38 untuk pekerja radiasi pada arah radial di perisai biologis sudah melemah memberikan nilai masing-masing sebesar 6,69915 µSv/jam dan 6,9964 µSv/jam pada posisi 215 cm dari pusat teras reaktor. Hasil analisis ini mengindikasikan bahwa pekerja radiasi aman dan terlindungi dari sumber radiasi neutron sesuai dengan persyaratan regulasi yang berlaku. Secara keseluruhan, dari hasil analisis perhitungan tersebut tampak bahwa model perisai radiasi dan perisai biologis telah memenuhi standar keselamatan radiasi yang dipersyaratkan. Hasil penelitian ini dapat digunakan untuk melengkapi data desain ketebalan perisai radiasi reaktor.Kata kunci: TRISO, pebble, RDE, laju dosis neutron, ICRP dan NCRP.

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“…The second one is that in thorium system there is bigger amount of the moderator. It causes significant increase of thermal inertia with all ensuing advantages such as safety and reliability [3,4,6,[11][12][13][14][15][16].…”

Section: Analysis Of Information Materials Of the Use Of Thorium As Nmentioning

confidence: 99%

“…Microfuel had bilayered coatings: layer 1: pyrolytic carbon (PyC) with the density of 1720 kg/m 3 ; layer 2: silicon carbide (SiC) with the density of 3210 kg/m 3 . Configurations of the fuel kernel, coatings, and fuel pellets (see Figure 1) were chosen on the basis of scientific results obtained in [3,4,6,[11][12][13][14][15][16].…”

Section: Calculation Model Of the High-temperature Gas-cooled Thoriummentioning

confidence: 99%

Gas-Cooled Thorium Reactor with Fuel Block of the Unified Design

Shamanin

Bedenko

Chertkov

et al. 2015

Advances in Materials Science and Engineering

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Scientific researches of new technological platform realization carried out in Russia are based on ideas of nuclear fuel breeding in closed fuel cycle and physical principles of fast neutron reactors. Innovative projects of low-power reactor systems correspond to the new technological platform. High-temperature gas-cooled thorium reactors with good transportability properties, small installation time, and operation without overloading for a long time are considered perspective. Such small modular reactor systems at good commercial, competitive level are capable of creating the basis of the regional power industry of the Russian Federation. The analysis of information about application of thorium as fuel in reactor systems and its perspective use is presented in the work. The results of the first stage of neutron-physical researches of a 3D model of the high-temperature gas-cooled thorium reactor based on the fuel block of the unified design are given. The calculation 3D model for the program code of MCU-5 series was developed. According to the comparison results of neutron-physical characteristics, several optimum reactor core compositions were chosen. The results of calculations of the reactivity margins, neutron flux distribution, and power density in the reactor core for the chosen core compositions are presented in the work.

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Thorium fuel performance assessment in HTRs

Cited by 8 publications

References 6 publications

Review of the microheterogeneous thoria‐urania fuel for micro‐sized high temperature reactors

Review of the microheterogeneous thoria‐urania fuel for micro‐sized high temperature reactors

Analisis Kuat Sumber Neutron Dan Perhitungan Laju Dosis Neutron Teras Awal Rde

Gas-Cooled Thorium Reactor with Fuel Block of the Unified Design

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