Comparison of the nuclear data libraries in the shielding calculation for the accelerator facility of the Proton Engineering Frontier Project in Korea

Lee, C. W.; Lee, Y. O.; Cho, Y. S.

doi:10.1051/ndata:07593

Cited by 2 publications

(2 citation statements)

References 2 publications

(2 reference statements)

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The level 2 classification, which is the criterion that distinguishes the large accelerator facilities from the small-scale RG, adopts the beam energy of 50 MeV or 50 MeV n −1 , and includes the low-energy criterion for heavy-ion beams in conjunction with the beam power considering the RAON accelerator that accelerates a uranium beam. Based on the previous bulk shielding and activation analysis results in the charge stripper section of the RAON accelerator [21], the energy of 10 MeV n −1 and corresponding beam power are proposed. This criterion is the same as for ion accelerators in German legislation.…”

Section: Classification Of Large Accelerator Facilitiesmentioning

confidence: 99%

An alternative proposal for the regulatory framework of the large accelerator facilities in the Korean Nuclear Safety Act

Jung¹,

Lee²,

Lee³

et al. 2021

J. Radiol. Prot.

View full text Add to dashboard Cite

Large accelerator facilities for scientific research and particle accelerators for radiotherapy have been constructed in Korea. The environments requiring radiological protection procedures have changed substantially and the legal requirements have also increased. However, the same regulatory criteria that are applied to small radiation-generating devices also apply to large accelerator facilities. This study evaluates an approach that uses new criteria based on radiological risk to classify different types of large accelerator facilities. To inform this study, regulations and licensing procedures adopted in various countries were reviewed. The radiological risks from different types of particle accelerators and different types of accelerated particles were investigated in relation to current and planned large accelerators in Korea. The investigation was based on neutron yield and induced radioactivity calculations undertaken using the Monte-Carlo code FLUKA. Based on this analysis, we propose two categories for large accelerator facilities. In the process of the facility construction through to getting an operation permit, we also propose a graded approach, which would require changes in the Korean Nuclear Safety Act. A two-step licensing procedure with a prior review and a final permit for accelerator operation is very practical and conservative in the view of radiation protection. The review process for the revision of the Nuclear Safety Act is currently in progress and a major aspect of this revision reflects the results of this study.

show abstract

Section: Classification Of Large Accelerator Facilitiesmentioning

confidence: 99%

An alternative proposal for the regulatory framework of the large accelerator facilities in the Korean Nuclear Safety Act

Jung¹,

Lee²,

Lee³

et al. 2021

J. Radiol. Prot.

View full text Add to dashboard Cite

show abstract

“…Most materials, in particular shielding materials such as concrete, are naturally heterogeneous or change their properties over time through wear. Moreover, the values of the cross-sections are taken from nuclear data libraries across the world and they can differ significantly between libraries [36]. This means there are large amounts of uncertainty on the coefficients, and this could have significant consequences on the system itself.…”

Section: Uncertainty Quantificationmentioning

confidence: 99%

Modern Monte Carlo Variants for Uncertainty Quantification in Neutron Transport

Graham

Parkinson

Scheichl

2018

Contemporary Computational Mathematics - A Celebration of the 80th Birthday of Ian Sloan

View full text Add to dashboard Cite

Dedicated to Ian H. Sloan on the occasion of his 80th birthday.Abstract We describe modern variants of Monte Carlo methods for Uncertainty Quantification (UQ) of the Neutron Transport Equation, when it is approximated by the discrete ordinates method with diamond differencing. We focus on the monoenergetic 1D slab geometry problem, with isotropic scattering, where the crosssections are log-normal correlated random fields of possibly low regularity. The paper includes an outline of novel theoretical results on the convergence of the discrete scheme, in the cases of both spatially variable and random cross-sections. We also describe the theory and practice of algorithms for quantifying the uncertainty of a linear functional of the scalar flux, using Monte Carlo and quasi-Monte Carlo methods, and their multilevel variants. A hybrid iterative/direct solver for computing each realisation of the functional is also presented. Numerical experiments show the effectiveness of the hybrid solver and the gains that are possible through quasi-Monte Carlo sampling and multilevel variance reduction. For the multilevel quasi-Monte Carlo method, we observe gains in the computational ε-cost of up to 2 orders of magnitude over the standard Monte Carlo method, and we explain this theoretically. Experiments on problems with up to several thousand stochastic dimensions are included.

show abstract

Comparison of the nuclear data libraries in the shielding calculation for the accelerator facility of the Proton Engineering Frontier Project in Korea

Cited by 2 publications

References 2 publications

An alternative proposal for the regulatory framework of the large accelerator facilities in the Korean Nuclear Safety Act

An alternative proposal for the regulatory framework of the large accelerator facilities in the Korean Nuclear Safety Act

Modern Monte Carlo Variants for Uncertainty Quantification in Neutron Transport

Contact Info

Product

Resources

About