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Nuclear Science and Technology ISSN 1810-5408 Nuclear Science and Technology Volume 9, Number 2, June 2019 Published by VIETNAM ATOMIC ENERGY SOCIETY VIETNAM ATOMIC ENERGY INSTITUTE NUCLEAR SCIENCE AND TECHNOLOGY Volume 9, Number 2, June 2019 Editorial Board Editor-in-chief Tran Huu Phat (VINATOM) Executive Editors Vuong Huu Tan (VARANS) Tran Chi Thanh (VINATOM) Cao Đình Thanh (VINATOM) Hoang Anh Tuan (VAEA) Editors Nguyen Kien Cuong (VINATOM) Le Hong Khiem (IOP) Nguyen Nhi Dien (VINATOM) Dao Tien Khoa (VINATOM) Nguyen Thi Kim Dung (VINATOM) Tran Hoai Nam (Duy Tan University) Ho Manh Dung (VINATOM) Dang Duc Nhan (VINATOM) Nguyen Nam Giang (VINATOM) Nguyen Hao Quang (VINATOM) Trinh Van Giap (VINATOM) Nguyen Mong Sinh (VINATOM) Le Ngoc Ha (108 Military Central Hospital) Tran Duc Thiep (IOP) Phan Son Hai (VINATOM) Dang Quang Thieu (VINATOM) Le Huy Ham (VAAS) Le Ba Thuan (VINATOM) Nguyen Quoc Hien (VINATOM) Nguyen Trung Tinh (VARANS) Le Van Hong (VINATOM) Tran Ngoc Toan (VINATOM) Nguyen Tuan Khai (VINATOM) Duong Thanh Tung (VARANS) Pham Dinh Khang (VINATOM) Nguyen Nu Hoai Vi (VARANS) Science Secretary Hoang Sy Than (VINATOM) .................................................................................................................................................................................................................... Copyright: ©2008 by the Vietnam Atomic Energy Society (VAES), Vietnam Atomic Energy Institute (VINATOM). Pusblished by Vietnam Atomic Energy Society, 59 Ly Thuong Kiet, Hanoi, Vietnam Tel: 84-24-39420463 Fax: 84-24-39424133 Email: [email protected] Vietnam Atomic Energy Institute, 59 Ly Thuong Kiet, Hanoi, Vietnam Tel: 84-24-39420463 Fax: 84-24-39422625 Email: [email protected] .................................................................................................................................................................................................................... Contents On Burnup Modelling Issues Associated with VVER–440 Fuels Branislav Vrban, Štefan Čerba, Jakub Lüley, Filip Osuský,Mikuláš Vorobeľ, Vladimír Nečas…………………………………………………………………………………………………... 01 Estimation of Tritium Production in VVER-440 Reactor Core During Normal Operation Štefan Čerba, Jakub Lüley, Branislav Vrban, Filip Osuský, Vladimír Nečas…………...... 10 Processing of the multigroup cross-sections for MCNP calculations Jakub Lüley, Branislav Vrban, Štefan Čerba, Filip Osuský, Vladimír Nečas.................... 17 Conceptual design of a small-pressurized water reactor using the AP1000 fuel assembly design Van Khanh Hoang, Viet Phu Tran, Van Thin Dinh, Hoai Nam Tran………………………… 25 Low-energy experiments at the S3 spectrometer S. Franchoo……………………………………………………………………………………………………….. 31 Dosimetric characteristics of 6 MV photons from TrueBeam STx medical linear accelerator: simulation and experimental data N. D. Ton, B. D. Linh, Q.T. Pham………………………………………………………………………… 37 Conceptual designing of a slow positron beam system using Simion simulation program Cao Thanh Long, Huynh Dong Phuong, Nguyen Trung Hieu, Tran Quoc Dung……….. 45 Nuclear Science and Technology, Vol.9, No. 2 (2019), pp. 01-09 On Burnup Modelling Issues Associated with VVER–440 Fuels Branislav Vrban1,2, Štefan Čerba1, Jakub Lüley1, Filip Osuský1, Mikuláš Vorobeľ1 and Vladimír Nečas1 1Slovak University of Technology in Bratislava, Faculty of Electrical Engineering and Information Technology, Institute of Nuclear and Physical Engineering, Ilkovičova 3, 812 19 Bratislava, Slovakia, 2B&J NUCLEAR Ltd., Alžbetin Dvor 145, 900 42 Miloslavov, Slovakia Email [email protected] (Received 12 November 2019, accepted 19 November 2019) Abstract: The paper investigates various computational modelling issues associated with VVER-440 fuel depletion, relevant to burnup credit. The SCALE system and the TRITON sequence are used for the calculations. The effects of variations in depletion parameters and used calculation methods on the isotopic vectors are investigated. The burnup behaviour of Gadolinium is quite important in actual core analysis, but its behaviour is somewhat complicated, requiring special treatment in numerical modelling and calculations. Therefore, a special part of the paper is devoted to the treatment of Gadolinium-bearing fuels. Moreover, some discussions on power normalization are also included. To assess the acquired modelling experience used to predict the VVER-440 spent fuel nuclide composition, the measured compositions of Novovoronezh NPP irradiated fuel assembly are compared to data calculated by TRITON sequence. The samples of fuel assembly with 3.6 wt. % U-235 enrichment underwent 4-cycle campaign of totally 1109 effective full power days in the core and cooling period of 1-13 years. Calculated concentrations are compared to measured values burdened with their experimental uncertainties for totally 47 nuclides. The calculated results show overall a good agreement for all nuclides, differences from measured are pointed out and discussed in the paper. Keywords: burnup, VVER 440, modelling, SCALE. I. INTRODUCTION consideration. Slovakia has four nuclear reactors generating half of its electricity and The prediction accuracy of burnup another two under construction. This paper calculations is a critical factor in the reactor investigates and summarizes modelling issues analysis sequence. The core properties depend associated with VVER-440 fuel depletion on the actual composition of the fuel; thus, the performed by the SCALE system [1]. The characteristics of the reactor core undergo effects of variations in the depletion parameters changes during burnup. Moreover, the isotopic and used calculation methods on the isotopic composition of the spent fuel discharged from vectors are investigated. The burnup behaviour the core is a key factor in both the operations of Gadolinium, a burnable poison in nuclear and the material control activities of the deep fuel, is quite important in actual core analysis; geological repository. An accurate estimate of therefore, a special part of the paper is devoted the time-dependent radionuclide inventory in to this issue. Finally, some discussions on this material is necessary to evaluate many power normalization are also included. Other spent fuel issues, including neutron and publications relevant to burnup modelling gamma-ray source terms for shielding analysis, issues for PWR can be found in [2,3]. To decay-heat source terms for temperature assess the ability of the SCALE system and the distribution and radiological and chemical associated nuclear data to predict the VVER- toxicity for environmental impact 440 spent fuel nuclide composition, the ©2019 Vietnam Atomic Energy Society and Vietnam Atomic Energy Institute ON BURNUP MODELLING ISSUES ASSOCIATED WITH VVER–440 FUELS measured compositions of Novovoronezh NPP triangular grid pattern. The assembly is irradiated fuel assembly are compared to data enclosed in a hexagonal wrapper with the calculated by the TRITON sequence in the last width across the flat equal to 145 mm (the 2nd part of the paper. The work done follows the generation FA). The FA and emergency reactor simplified specification of the computational control assemblies (ERC) are positioned in a benchmark based on the #2670 ISTC project hexagonal grid with a spacing of 147 mm. The [4] providing VVER-440 data for 8 samples fuel rods are in the bundle in a triangular grid cut outs of 4 fuel pins of the fuel assembly pattern with a pitch of 12.3 mm. The fuel rod (FA) No. D26135 with the average reached claddings are made of the E110 zirconium burnup 38.5 MWd/kgU. The #2670 ISTC alloy (Zr + 1% Nb), while the wrapper tubes of project has was carried out between years 2003 FA and ERC are made of the E125 zirconium and 2005. Measurements of samples cut out of alloy (Zr + 2.5% Nb). The modelled outside were performed in RIAR Dimitrovgrad, diameter of fuel rod cladding is 9.1 mm and the Russia, the final project report is publicly inside diameter is 7.75 mm. The cladding accessible [6]. The FA irradiation was done houses a fuel column assembled of uranium during the 15 - 18 core loads in the fourth dioxide pellet. Generally, several types of power unit of Novovoronezh NPP. profiled fuel assemblies are used to maintain power peaking factors under the design limits. II. METHODS AND TECHNIQUES A Gd2O3 absorber is integrated with a mass content of 3.35% into number of FAs to aid A. VVER-440 geometry model description fuel profiling. The profiling diagrams with All the current VVER-440 fuel various initial enrichments and locations of assemblies used in Slovakia are hexagonal and fuel bundles used in self-developed 2D SCALE the fuel rods are placed in the assembly in a models are shown in Fig. 1. a) ERC fuel part - 3.84 wt % U-235 b) FA - 4.25 wt% U-235 c) FA & ERC fuel part - 4.87 wt % U-235 Fig. 1. Profiling diagram for fuel rod bundles used in computational model 2 BRANISLAV VRBAN et al. B. Calculation methodology modelled with temperature of 933 K and the An accurate treatment of neutron temperature of structural materials and water transport and depletion in VVER-440 fuel coolant is 555 K. The fuel pellet density is assemblies characterized by heterogeneous and 10.55 g/cc and the density of zirconium alloys complex design requires the use of advanced equals 6.55 g/cc. Very fine depletion steps computational tools. The depletion module (<0.5 MWd/kgHM) are used before TRITON [5], included in SCALE 6.1.3 code Gadolinium peak reactivity to track the fast system developed by ORNL, was used to poison concertation changes.
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