A new SCWR fuel assembly with two-row fuel rods between the hexagonal moderator channels

Wang, Lianjie; Qin, Dong; Li, Qing; Xia, Bangyang

doi:10.1016/j.anucene.2013.02.029

Cited by 1 publication

(2 citation statements)

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“…For the hexagonal fuel assemblies we consider the hexagon with sides " " and center "O" as shown in Figure 1. The distance between opposite sides is denoted by "Δ " and the height is denoted by "Δ " [3]. The area and volume of the hexagon can be written as…”

Section: Reactor Core Simulation Modelmentioning

confidence: 99%

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Modification of Neutron Kinetic Code for Plate Type Fuel Nuclear Reactor

Khan

Yang

2013

Science and Technology of Nuclear Installations

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The research is conducted on the modification of neutron kinetic code for the plate type fuel nuclear reactor. REMARK is a neutron kinetic code that works only for the cylindrical type fuel nuclear reactor. In this research, our main emphasis is on the modification of this code in order to be applicable for the plate type fuel nuclear reactor. For this purpose, detailed mathematical studies have been performed and are subjected to write the program in Fortran language. Since REMARK code is written in Fortran language, so we have developed the program in Fortran and then inserted it into the source library of the code. The main emphasis is on the modification of subroutine in the source library of the code for hexagonal fuel assemblies with plate type fuel elements in it. The number of steps involved in the modification of the code has been included in the paper. The verification studies were performed by considering the small modular reactor with hexagonal assemblies and plate type fuel in it to find out the power distribution of the reactor core. The purpose of the research is to make the code work for the hexagonal fuel assemblies with plate type fuel element.

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Section: Reactor Core Simulation Modelmentioning

confidence: 99%

“…The main concern of our research is to modify the nuclear reactor core for hexagonal fuel assemblies. The research on the new developed hexagonal fuel assembly design has already been done on the supercooled water reactor (SCWR) to show the moderation capability for the hexagonal fuel assemblies [3,4].…”

Section: Introductionmentioning

confidence: 99%

Modification of Neutron Kinetic Code for Plate Type Fuel Nuclear Reactor

Khan

Yang

2013

Science and Technology of Nuclear Installations

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show abstract

A new SCWR fuel assembly with two-row fuel rods between the hexagonal moderator channels

Cited by 1 publication

References 5 publications

Modification of Neutron Kinetic Code for Plate Type Fuel Nuclear Reactor

Modification of Neutron Kinetic Code for Plate Type Fuel Nuclear Reactor

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