Rigorous mcnp based shutdown dose rate calculations: computational scheme, verification calculations and application to ITER

Chen, Ye; Fischer, U.

doi:10.1016/s0920-3796(02)00144-8

Cited by 118 publications

(40 citation statements)

References 2 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…Shutdown dose rate calculations will be performed in the near future on the newly developed model. To be able to perform such calculations, the authors will rely on the on-going implementation of the so-called "rigorous-two-step" methodology [12] into TRIPOLI-4® [13]. Future work should also consider the optimization of the variance reduction scheme in TRIPOLI-4®, necessary to obtain reasonable statistical accuracy in the neutron flux meshes.…”

Section: Discussionmentioning

confidence: 99%

A Monte-Carlo Benchmark of TRIPOLI-4® and MCNP on ITER neutronics

et al. 2017

View full text Add to dashboard Cite

Abstract. Radiation protection and shielding studies are often based on the extensive use of 3D Monte-Carlo neutron and photon transport simulations. ITER organization hence recommends the use of MCNP-5 code (version 1.60), in association with the FENDL-2.1 neutron cross section data library, specifically dedicated to fusion applications. The MCNP reference model of the ITER tokamak, the 'C-lite', is being continuously developed and improved. This article proposes to develop an alternative model, equivalent to the 'C-lite', but for the Monte-Carlo code TRIPOLI-4®. A benchmark study is defined to test this new model. Since one of the most critical areas for ITER neutronics analysis concerns the assessment of radiation levels and Shutdown Dose Rates (SDDR) behind the Equatorial Port Plugs (EPP), the benchmark is conducted to compare the neutron flux through the EPP. This problem is quite challenging with regard to the complex geometry and considering the important neutron flux attenuation ranging from 10 14 down to 10 8 n•cm -2 •s -1 . Such code-to-code comparison provides independent validation of the Monte-Carlo simulations, improving the confidence in neutronic results.

show abstract

Section: Discussionmentioning

confidence: 99%

A Monte-Carlo Benchmark of TRIPOLI-4® and MCNP on ITER neutronics

et al. 2017

View full text Add to dashboard Cite

show abstract

“…Shutdown dose rate calculations were performed utilizing the Rigorous 2-Step (R2S) approach [4]. The methodological approach for the present neutronics analysis is composed of three computational steps: 1) neutron transport calculations with the McDeLicious-11 Monte Carlo code [5] using the FENDL-3, Starter Library, Release 2 (FENDL-3/SLIB2) cross-section library [6], 2) activation calculations with the FISPACT-2007 inventory code [7] and EAF-2007 activation cross-section data, and 3) decay photon transport calculations with the Monte Carlo code MCNP5 [8].…”

Section: Calculation Code and Methodologymentioning

confidence: 99%

“…In this analysis only the contribution from specimens irradiated in HFTM was estimated and no detailed analysis for entire HFTM nor TC has been carried out so far. Therefore, this study has been devoted to obtain a detailed map of the radiation dose resulting from the whole HFTM and TC activated by utilizing the "Rigorous 2-Step (R2S)" approach developed at KIT [4]. The paper explains the calculation approach.…”

mentioning

confidence: 99%

Shutdown dose calculations for the IFMIF test facility and the high flux test module

Kondo

Arbeiter²,

Fischer³

2014

Progress in Nuclear Science and Technology

View full text Add to dashboard Cite

This work presents neutronic analyses to support the design of the test facility of the International Fusion Materials Irradiation Facility (IFMIF) in the framework of the Broader Approach activities. In order to evaluate the necessary biological shielding thickness and the reliability of remote handling tools for activated components inside the Test Cell, a detailed activation analysis has been carried out to obtain a detailed residual dose map resulting from the entire High Flux Test Module and Test Cell by utilizing the McDeLicious-11 Monte Carlo code and the mesh-tally based rigorous 2-Step approach (R2Smesh) developed at KIT. The absorbed dose rate expected at the working place of remote handling tools inside the Test Cell is approximately 100 Gy/h. A wall thickness of 150 cm for heavy concrete can be used as the design basis for hot cells in the test facility.

show abstract

“…Для этого в настоящее время проводятся расчёты дозы ней-тронного излучения, которую магнит получит в течение срока своей службы. Эти расчёты ведутся прямым одноступенчатым методом, разработанным коллективом ИТЭР и ENEA [22,23], и более точным двухсту-пенчатым методом, разработанным в Исследовательском центре Карлсруэ (FZK) [24]. Анализ мощности дозы от таких радиоактивных элементов, как Co, Cr и Nb, проводился для длительной работы токамака KSTAR.…”

Section: исследования в республике кореяunclassified

Studies of Radioactive Material Manаgement in the Frame of the Iea Cooperative Program on the Environmental, Safety and Economic Aspects of Fusion Power

Zucchetti

Kolbasov

Riva

et al. 2016

PAST-TF

View full text Add to dashboard Cite

В данной статье рассматриваются некоторые результаты организованных Международным энергетическим агентством иссле-дований технологических проблем обращения с радиоактивными материалами термоядерных энергетических установок (ТЭУ) после извлечения из них заменяемых компонентов и после вывода ТЭУ из эксплуатации. Основные исследования направлены на разработку требований по выводу облучённых материалов из-под контроля надзорных органов, определение возможности применения ручных процедур или дистанционного оборудования при переработке материалов для их возвращения в производ-ственный цикл, непрерывную оценку радиационной опасности от облучённых материалов термоядерных установок и их детри-тизацию. Чтобы расширить фронт работ по выбору функциональных материалов для первой стенки термоядерного реактора (помимо вольфрама как основного кандидатного материала покрытия), рассмотрены потенциально альтернативные материалы, такие как цирконий, ниобий, молибден, гафний и тантал, с точки зрения их возможной активации нейтронами, распыления в результате эрозии и переосаждения, влияния на переходные процессы в плазме и возможности их возвращения в производст-венный цикл.Ключевые слова: радиоактивные материалы, безопасность термоядерной установки, Международное энергетическое агентст-во, нейтронная активация, тритий. Some results of the collaborative studies organized by the International Energy Agency (IEA) in the area of technological problems of the fusion radioactive materials management following the withdrawing of replaceable components from the fusion facilities and decommissioning of these facilities are addressed in this paper. Key issues include clearance conditions, hands-on and remote recycling procedures, radioactive fusion material hazard assessment, and detritiation of activated materials. To broaden the options for fusion development, researchers examined five potentially alternative high-Z materials: zirconium, niobium, molybdenum, hafnium, and tantalum from four standpoints: neutron-induced activation, sputter erosion/redeposition, plasma transient response and recycling possibility. STUDIES OF RADIOACTIVE MATERIAL MANАGEMENT IN THE FRAME OF THE IEA COOPERATIVE PROGRAM ON THE ENVIRONMENTAL, SAFETY AND ECONOMIC ASPECTS OF FUSION POWER

show abstract

Rigorous mcnp based shutdown dose rate calculations: computational scheme, verification calculations and application to ITER

Cited by 118 publications

References 2 publications

A Monte-Carlo Benchmark of TRIPOLI-4® and MCNP on ITER neutronics

A Monte-Carlo Benchmark of TRIPOLI-4® and MCNP on ITER neutronics

Shutdown dose calculations for the IFMIF test facility and the high flux test module

Studies of Radioactive Material Manаgement in the Frame of the Iea Cooperative Program on the Environmental, Safety and Economic Aspects of Fusion Power

Contact Info

Product

Resources

About