ANALYSIS OF DOSE RATES AROUND THE SLOVENIAN SILO-TYPE LILW REPOSITORY USING ADVANTG [PDF]
EPJ Web of Conferences, 2021 The ADVANTG code was used to analyze dose rates from the proposed Slovenian silo-type low and intermediate level waste (LILW) repository. Detailed calculations of dose rates are challenging as gamma-sources are located in thick concrete containers and ...
Bor Koß, Domen Kotnik, Luka Snoj
exaly +3 more sources
Analysis of DD, TT and DT Neutron Streaming Experiments with the ADVANTG Code [PDF]
EPJ Web of Conferences, 2020 The paper presents an analysis of DD, TT and DT neutron streaming benchmark experiments with the recently released hybrid transport code ADVANTG (AutomateD VAriaNce reducTion Generator).
Rosaria Villari +2 more
exaly +3 more sources
Reduced Variance using ADVANTG in Monte Carlo Calculations of Dose Coefficients to Stylized Phantoms [PDF]
EPJ Web of Conferences, 2017 The estimation of dose coefficients of external radiation sources to the organs in phantoms becomes increasingly difficult for lower photon source energies. This study focus on the estimation of photon emitters around the phantom.
Keith Eckerman
exaly +3 more sources
Activation calculation for the dismantling and decommissioning of a light water reactor using MCNP™ with ADVANTG and ORIGEN-S [PDF]
EPJ Web of Conferences, 2017 The decommissioning of a light water reactor (LWR), which is licensed under § 7 of the German Atomic Energy Act, following the post-operational phase requires a comprehensive licensing procedure including in particular radiation protection aspects and ...
Schlömer Luc +2 more
exaly +3 more sources
Use of ADVANTG to analyse skyshine γ-dose rates around a silo type LILW repository
Annals of Nuclear Energy, 2020 Abstract MCNP and the ADVANTG code were used to analyse γ-dose rates for the future Slovenian LILW repository. Using ADVANTG’s variance reduction technique, different detailed calculations of γ-dose rates were achievable in a reasonable time, whereby the analogue MCNP simulations were accelerated up to 9500 times.
Bor Koß, Domen Kotnik, Luka Snoj
exaly +2 more sources
Analysis of dpa Rates in the HFIR Reactor Vessel using a Hybrid Monte Carlo/Deterministic Method*
EPJ Web of Conferences, 2016 The Oak Ridge High Flux Isotope Reactor (HFIR), which began full-power operation in 1966, provides one of the highest steady-state neutron flux levels of any research reactor in the world.
Risner J.M., Blakeman E.D.
doaj +2 more sources
APPLICATION OF THE JSIR2S CODE PACKAGE FOR SHUTDOWN DOSE RATE CALCULATIONS ON JET [PDF]
EPJ Web of Conferences, 2021 In this paper we present a computational exercise for shut-down dose rate calculations for the JET tokamak using the in-house developed JSIR2S code package as part of its validation.
Ambrožič Klemen +3 more
doaj +1 more source
Assessment of the gamma and neutron dose field around the closed-water activation loop at the JSI TRIGA reactor [PDF]
EPJ Web of Conferences, 2023 A closed-water activation loop is being built at the Jožef Stefan Institute TRIGA reactor in Slovenia to serve as a well-defined and stable source of high-energy gamma rays and neutrons.
Kotnik Domen, Snoj Luka, Lengar Igor
doaj +1 more source
Determination of backscattered neutrons/gammas from open beam port of a research reactor [PDF]
EPJ Web of Conferences, 2020 Neutron and gamma dose rate calculations were carried out around horizontal beam tube no. 5 at the Jožef Stefan Institute (JSI) TRIGA Mark II research reactor.
Jazbec Anže +4 more
doaj +1 more source
Frontiers in Energy Research, 2023 In a typical pressurized water reactor, neutron detectors located outside the reactor core monitor reactor power. In addition, they are also used to measure the reactivity of the control rods.
Tanja Goričanec +8 more
doaj +1 more source