Used nuclear fuels

In this paper, an analysis of the Integral Inherently Safe LWR design (I2S-LWR), a reactor concept developed by an international collaboration led by the Georgia Institute of Technology, within a US DOE Nuclear Energy University Program (NEUP) Integrated Research Project (IRP) is considered.

9p christabelhuynh 30-05-2020 16 2   Download

This work is intended to cross check the new capabilities of the fuel cycle scenario code TR_EVOL.This process has been divided in two stages. The first stage is dedicated to check the improvements in the nuclear fuel mass balance estimation using the available datafor the Spanish nuclear fuel cycle.

8p christabelhuynh 30-05-2020 9 1   Download

This paper discusses concepts for three-component fuel bundles containing plutonium, uranium and thorium for use in pressurised heavy water reactors, and cases for and against implementation of such a nuclear energy system in the United Kingdom.

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This study has been made in an attempt to find the structural integrity of the Chashma Nuclear power plant-1 FA skeleton at room temperature. The finite element (FE) analysis has been performed using ANSYS, in orderto determinethe elongationofthe FAskeleton as wellas the locationofmax. stress and stresses developedin axial direction under tensile load of 9800 N or 2 g being the FA handling or lifting load [Y. Zhang et al., Fuel Assembly Design Report, SNERDI, China, 1994].

6p christabelhuynh 30-05-2020 25 1   Download

Comparisons of calculated and experimental isotopic compositions of used nuclear fuels can provide valuable information on the quality of nuclear data involved in neutronic calculations.

19p christabelhuynh 29-05-2020 10 1   Download

This study presents a coolant void reactivity analysis of Canada Deuterium Uranium (CANDU)- 6 and Advanced Canada Deuterium Uranium Reactor-700 (ACR-700) fuel lattices using a Monte Carlo code. The reactivity changes when the coolant was voided were assessed in terms of the contributions of four factors and spectrum shifts. In the case of single bundle coolant voiding, the contribution of each of the four factors in the ACR-700 lattice is large in magnitude with opposite signs, and their summation becomes a negative reactivity effect in contrast to that of the CANDU-6 lattice.

11p minhxaminhyeu4 26-06-2019 19 1   Download

Increasing the operation cycle length can be an important goal in the fuel reload design of a nuclear reactor core. In this research paper, a new optimization approach, electromagnetism mechanism (EM), is applied to the fuel arrangement design of the Bushehr WWER1000 core. For this purpose, a neutronic solver has been developed for calculating the required parameters during the reload cycle of the reactor. In this package, two modules have been linked, including PARCS v2.7 and WIMS-5B codes, integrated in a solver for using in the fuel arrangement optimization operation.

11p minhxaminhyeu4 26-06-2019 39 1   Download