Applicability of RANS models and pressure drop in edge subchannels for 19-pin wire-wrapped fuel bundle channel in CiADS [PDF]
Heliyon, 2023 The accelerator-driven subcritical system has a strong transmutation ability and high inherent safety, and it is internationally recognized as the most promising long-life nuclear waste disposal device.
Dajun Fan +10 more
doaj +4 more sources
Numerical Study on Influence of Cross Flow on Rewetting of AHWR Fuel Bundle [PDF]
The Scientific World Journal, 2014 Numerical study on AHWR fuel bundle has been carried out to assess influence of circumferential and cross flow rewetting on the conduction heat transfer.
Mithilesh Kumar +3 more
doaj +2 more sources
CHF Enhancement of Advanced 37-Element Fuel Bundles [PDF]
Science and Technology of Nuclear Installations, 2015 A standard 37-element fuel bundle (37S fuel bundle) has been used in commercial CANDU reactors for over 40 years as a reference fuel bundle. Most CHF of a 37S fuel bundle have occurred at the elements arranged in the inner pitch circle for high flows and
Joo Hwan Park +2 more
doaj +3 more sources
Nuclear Energy and Technology, 2015 Different fuel element bundle models used to calculate the coolant and fuel cladding temperatures inside fuel assemblies have been analyzed as applied to sodium-cooled fast-neutron reactors. The drawbacks of the existing models have been identified.
B.B. Tikhomirov, V.M. Poplavsky
doaj +3 more sources
ASSESSMENT OF HEAT TRANSFER IN FUEL CHANNEL OF INDIAN PHWR UNDER POSTULATED LARGE BREAK LOSS OF COOLANT ACCIDENT: EXPERIMENTAL AND NUMERICAL STUDY [PDF]
EPJ Web of Conferences, 2021 The behaviour of the channel under postulated large break LOCA scenario had been a prime safety concern. The radiative heat transfer is predominant in a channel when the convective cooling environment is marred. The estimation of temperature distribution
Ajay Ketan, Kumar Ravi, Gupta Akhilesh
doaj +1 more source
DESIGN AND INVESTIGATION OF WEIGHT BUNDLE SIMULATOR FOR INDIAN PHWR USING APDL - A THERMAL ASPECT [PDF]
EPJ Web of Conferences, 2021 Under a postulated scenario of Loss of Coolant Accident (LOCA) with un-availability of emergency core cooling system (ECCS) for Indian Pressurized Heavy Water Reactor (IPHWR), the channel integrity needs to be assured.
Bhadauria Madhuri +2 more
doaj +1 more source
Thermo-Hydraulic Investigation of Nanofluid as a Coolant in VVER-440 Fuel Rod Bundle [PDF]
Transport Phenomena in Nano and Micro Scales, 2015 The main purpose of this study is to perform numerical simulation of nanofluids as the coolant in VVER-440 fuel rod bundle. The fuel rod bundle contains 60 fuel rods with length of 960 mm and 4 spacer grids. In VVER-440 fuel rod bundle the coolant fluid (
S. Jalili Palandi +2 more
doaj +1 more source
Determination of burnup limit for CANDU 6 fuel using Monte-Carlo method
Nuclear Engineering and Technology, 2021 KHNP recently has obtained the approval for the commercialization of the modified 37-element (or 37 M) fuel bundle and now is loading the 37 M fuel bundles in CANDU-6 reactors in KOREA. One of the main issues for approval was the burnup limit.
Eun-ki Lee
doaj +1 more source
Post-Irradiation Mechanical Properties Prediction of Al 6070 of MTR-Fuel Bundle for Cutting Process
Jurnal Ilmiah SINERGI, 2022 The Al 6070 is the side plate material of the MTR-fuel plate bundle. These post-irradiation mechanical properties will be used in the side plate cutting process to obtain certain plates from the MTR-fuel plate bundle. This activity is part of a series of
Antonio Gogo Hutagaol +3 more
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LWR nuclear fuel bundle data for use in fuel bundle handling [PDF]
, 1979 Although increasing numbers of spent light water reactor (LWR) fuel bundles are moved into storage, no handling equipment is set up to manipulate all of the various types of fuel bundles. This report summarizes fuel bundle information of interest to the designer of such handling equipment.
Weihermiller, W.B., Allison, G.S.
openaire +2 more sources