Results 11 to 20 of about 65 (46)

Shielding analyses supporting the Lithium loop design and safety assessments in IFMIF-DONES

Nuclear Engineering and Technology, 2023
The assessment of radiation fields in the lithium loop pipes and dump tank during the operation were performed for International Fusion Materials Irradiation Facility – DEMO-Oriented NEutron Source (IFMIF-DONES) in order to obtain the radiation dose-rate
Gediminas Stankunas, Yuefeng Qiu, Francesco Saverio Nitti, Juan Carlos Marugán   +3 more
doaj   +1 more source

ASUSD nuclear data sensitivity and uncertainty program package: Validation on fusion and fission benchmark experiments

Nuclear Engineering and Technology, 2021
Nuclear data (ND) sensitivity and uncertainty (S/U) quantification in shielding applications is performed using deterministic and probabilistic approaches. In this paper the validation of the newly developed deterministic program package ASUSD (ADVANTG + 
Bor Kos, Aljaž Čufar, Ivan A. Kodeli
doaj   +1 more source

Evaluation and Testing of the ADVANTG Code on SNM Detection [PDF]

, 2013
Pacific Northwest National Laboratory (PNNL) has been tasked with evaluating the effectiveness of ORNL’s new hybrid transport code, ADVANTG, on scenarios of interest to our NA-22 sponsor, specifically of detection of diversion of special nuclear material (SNM).
Shaver, Mark W., Casella, Andrew M., Wittman, Richard S., Hayes, John W.   +3 more
openaire   +2 more sources

ADVANTG An Automated Variance Reduction Parameter Generator [PDF]

, 2013
The primary objective of ADVANTG is to reduce both the user effort and the computational time required to obtain accurate and precise tally estimates across a broad range of challenging transport applications. ADVANTG has been applied to simulations of real-world radiation shielding, detection, and neutron activation problems.
Mosher, Scott W., Bevill, Aaron M., Johnson, Seth R., Ibrahim, Ahmad M., Daily, Charles R., Evans, Thomas M., Wagner, John C., Johnson, Jeffrey O.   +7 more
openaire   +2 more sources

Comparing the performance of two hybrid deterministic/Monte Carlo transport codes in shielding calculations of a spent fuel storage cask

Nuclear Engineering and Technology, 2019
This study systematically compared two hybrid deterministic/Monte Carlo transport codes, ADVANTG/MCNP and MAVRIC, in solving a difficult shielding problem for a real-world spent fuel storage cask.
Po-Chen Lai, Yu-Shiang Huang, Rong-Jiun Sheu   +2 more
doaj   +1 more source

PWR Facility Dose Modeling Using MCNP5 and the CADIS/ADVANTG Variance-Reduction Methodology [PDF]

, 2007
The feasibility of modeling a pressurized-water-reactor (PWR) facility and calculating dose rates at all locations within the containment and adjoining structures using MCNP5 with mesh tallies is presented. Calculations of dose rates resulting from neutron and photon sources from the reactor (operating and shut down for various periods) and the spent ...
Blakeman, Edward D, Peplow, Douglas E., Wagner, John C, Murphy, Brian D, Mueller, Don   +4 more
openaire   +2 more sources

Advanced Monte Carlo analysis of ex-vessel neutron dosimetry for cycle 25 of Krško nuclear power plant

Nuclear Engineering and Technology
This paper presents the results of Monte Carlo neutron transport calculations performed for the containment building of the Krško Nuclear Power Plant. The calculations were performed using the Monte Carlo N-Particle Transport Code (MCNP) in combination ...
Tanja Goričanec, Benjamin Barbarič, Vladimir Radulović, Dušan Čalič, Luka Snoj, Marjan Kromar   +5 more
doaj   +1 more source

Shielding analysis and optimization of IFMIF-DONES test cell floor bolt penetrations using MCNP and advanced variance reduction techniques

Nuclear Engineering and Technology
This study presents a shielding analysis and safety assessment for the Test Cell (TC) floor of the IFMIF-DONES (International Fusion Material Irradiation Facility-DEMO Oriented NEutron Source), focusing on the impact of mounting bolt penetrations and ...
Gediminas Stankunas, Benjaminas Togobickij, Simona Breidokaite, Dilmurod Tuymurodov, Andrius Tidikas   +4 more
doaj   +1 more source

Dose Rate Evaluation for the ES-3100 Package with HEU Content Using MCNP, ADVANTG, Monaco, and MAVRIC

Nuclear Technology, 2018
AbstractThis paper presents a comparative study of dose rate calculations for the ES-3100 package with highly enriched uranium (HEU) content for different source configurations using the following ...
openaire   +4 more sources

A combination of PD-1 and TIGIT immune checkpoint inhibitors elicits a strong anti-tumour response in mesothelioma

Journal of Experimental & Clinical Cancer Research
Background Finding effective and curative treatment for mesothelioma remains challenging. While the introduction of immunotherapy combinations using ipilimumab (anti-CTLA-4) and nivolumab (anti-PD-1) have offered hope for some patients, a large ...
Huaikai Shi, Ta-Kun Yu, Ben Johnson, Sakthi Priya Selvamani, Ling Zhuang, Kenneth Lee, Sonja Klebe, Samuel Smith, Kirby Wong, Kate Chen, Georgina Clark, Emma M. Rath, Holly Pearson, David Gallego Ortega, Anthony Linton, Steven Kao, Pablo Silveira, Yuen Yee Cheng   +17 more
doaj   +1 more source