Fuel Burnup and Fuel Management

2019 ◽  
pp. 501-521
Author(s):  
Bahman Zohuri
Keyword(s):  
Fuel Burnup ◽  
Fuel Management

scholarly journals Fuel burnup analysis and fuel management for TRIGA Mark III research reactor

2019 ◽  
Vol 1285 ◽  
pp. 012044
Author(s):  
K Tiyapun ◽  
C Tippayakul ◽  
S Wetchagarun
Keyword(s):  
Research Reactor ◽  
Fuel Burnup ◽  
Fuel Management

Fuel burnup, fuel management, and fuel cycle physics

2021 ◽  
pp. 331-372
Author(s):  
P. Mohanakrishnan ◽  
K. Umasankari
Keyword(s):  
Fuel Cycle ◽  
Fuel Burnup ◽  
Fuel Management

scholarly journals ANALYSES OF FUEL BURNUP CALCULATIONS OF KARTINI REACTOR BASED ON THE NEW CALCULATION SCHEME

2016 ◽  
Vol 17 (2) ◽  
pp. 91
Author(s):  
Tegas Sutondo
Keyword(s):  
Fuel Element ◽  
Epithermal Neutron ◽  
Management Program ◽  
Calculation Scheme ◽  
Fuel Burnup ◽  
Fuel Management ◽  
Present Scheme ◽  
Present Practice ◽  
The Difference ◽  
Burnup Calculation

ABSTRACT ANALYSES OF FUEL BURNUP CALCULATIONS OF KARTINI REACTOR BASED ON THE NEW CALCULATION SCHEME. It has been described a new scheme of fuel burnup calculation, intended to improve the present practice used at Kartini reactor. The improvement includes the use of power distributions, which will be used as the base for estimating the burnup of each individual fuel element, and the inclusion of epithermal neutron which will affect to the burnup rates and the total fuel consumed. A small computation program was then made to perform calculations based on the two calculation schemes, and to see the differences. The results indicate that the proposed scheme results in higher estimated value against that of the present scheme, and the differences tends to increase linearly with the cumulative burnups. For each cumulative burnup of 30 MWD the difference could reach about 9.87 % which is around 3.7 gram for the whole core. It can be concluded that the proposed approach could improve the present’s practice of burnup estimation, especially for each individual fuel element which is important to the in-core fuel management program.

A new hybrid method for multi-objective fuel management optimization using parallel PSO-SA

2014 ◽  
Vol 76 ◽  
pp. 112-121 ◽  
Author(s):  
F. Khoshahval ◽  
A. Zolfaghari ◽  
H. Minuchehr ◽  
M.R. Abbasi
Keyword(s):  
Hybrid Method ◽  
Fuel Management ◽  
Multi Objective ◽  
Management Optimization

scholarly journals Decomposition Analysis of Void Reactivity Coefficient for Innovative and Modified BWR Assemblies

2014 ◽  
Vol 2014 ◽  
pp. 1-9 ◽  
Author(s):  
Andrius Slavickas ◽  
Raimondas Pabarčius ◽  
Aurimas Tonkūnas ◽  
Gediminas Stankūnas
Keyword(s):  
Cross Section ◽  
Safety Concern ◽  
Functional Module ◽  
Decomposition Analysis ◽  
Fuel Burnup ◽  
Mox Fuel ◽  
High Enrichment ◽  
Reactivity Coefficient ◽  
The Impact ◽  
Irradiation Cycle

The decomposition analysis of void reactivity coefficient for innovative BWR assemblies is presented in this paper. The innovative assemblies were loaded with high enrichment UO2and MOX fuels. Additionally the impact of the moderation enhancement on the void reactivity coefficient through a full fuel burnup discharge interval was investigated for the innovative assembly with MOX fuel. For the numerical analysis the TRITON functional module of SCALE code with ENDF/B-VI cross section library was applied. The obtained results indicate the influence of the most important isotopes to the void reactivity behaviour over a fuel burnup interval of 70 GWd/t for both UO2and MOX fuels. From the neutronic safety concern positive void reactivity coefficient values are observed for MOX fuel at the beginning of the fuel irradiation cycle. For extra-moderated assembly designs, implementing 8 and 12 water holes, the neutron spectrum softening is achieved and consequently the lower void reactivity values. Variations in void reactivity coefficient values are explained by fulfilled decomposition analysis based on neutrons absorption reactions for separate isotopes.

Fast Reactor Fuel Burnup

1965 ◽  
Vol 1 (1) ◽  
pp. 55-61 ◽  
Author(s):  
F. R. Channon ◽  
J. D. Luoma ◽  
E. D. Frankhouser
Keyword(s):  
Fast Reactor ◽  
Reactor Fuel ◽  
Fuel Burnup ◽  
Fast Reactor Fuel
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