Design of a new Small Modular Nuclear Reactor using TVS-2M Fuel Assemblies and Fuel Depletion analysis during the fresh-core cycle length

2021 ◽  
Vol 385 ◽  
pp. 111540
Author(s):  
M.H. Zahedi yeganeh ◽  
G.R. Ansarifar
Keyword(s):  
Cycle Length ◽  
Nuclear Reactor ◽  
Fuel Assemblies

Thermohydrodynamic investigations of spacing lattices of rod fuel assemblies in a nuclear reactor

Atomic Energy ◽  
2000 ◽  
Vol 88 (1) ◽  
pp. 74-75
Author(s):  
A. I. Emel'yanov ◽  
S. Yu. Sarvin
Keyword(s):  
Nuclear Reactor ◽  
Fuel Assemblies

Implementation of Erbia With ZrB2 in 17×17 Assemblies for a 4-Loop Core With a 24-Month Cycle

2002 ◽  
Author(s):  
James E. Platte ◽  
Ernesto Pitruzzella ◽  
Youssef Shatilla ◽  
Baard Johansen
Keyword(s):  
Fuel Assembly ◽  
Temperature Coefficient ◽  
Cycle Length ◽  
Zirconium Diboride ◽  
Fuel Rods ◽  
Fuel Assemblies ◽  
Burnable Absorber

There are many types of burnable absorbers currently used in power reactors. They are used to provide reactivity and power peaking control. Westinghouse reactors most commonly use Zirconium Diboride Integral Fuel Burnable Absorbers (ZrB2) while Combustion Engineering reactors most commonly use Erbia Integral Fuel Burnable Absorbers (Erbia) in Combustion Engineering reactors. This paper documents the study to determine the effect of placing Erbia and ZrB2 within a Westinghouse 17×17 fuel assembly, and the effect of these ZrB2/Erbia assemblies on the physics characteristics of a representative Westinghouse 4-loop, 24 month cycle length design. The study consisted first of producing optimal within-assembly burnable absorber configurations where ∼25% of the ZrB2-bearing fuel rods within an assembly were replaced with Erbia-bearing fuel rods. This ratio was selected in order to provide an effective balance between potential peaking factor improvements and the known Erbia disadvantage of increased residual absorber penalty compared with ZrB2. The optimal patterns were selected as the ones that most reduced the assembly-wise cumulative peak-to-average rod power during the depletion compared with existing all-ZrB2 BA configurations with the same BA rod quantity loading. The second part of this study consisted of substituting various quantities of these ZrB2/Erbia feed fuel assemblies in a representative Westinghouse 4-loop, 24 month cycle core design to study the effect on power peaking factors, moderator temperature coefficient (MTC), and cycle length.

Mechanical fragmentation of nuclear reactor fuel assemblies by the double cutting method

Atomic Energy ◽  
1994 ◽  
Vol 77 (3) ◽  
pp. 676-680 ◽  
Author(s):  
B. V. Voitsekhovskii ◽  
V. L. Istomin ◽  
V. V. Mitrofanov
Keyword(s):  
Nuclear Reactor ◽  
Reactor Fuel ◽  
Cutting Method ◽  
Nuclear Reactor Fuel ◽  
Fuel Assemblies ◽  
Mechanical Fragmentation

scholarly journals Minimizing Power Peaking Factor of BEAVRS-based Reactor Using Polar Bear Optimization Algorithms

2021 ◽  
Vol 927 (1) ◽  
pp. 012004
Author(s):  
Amila Amatullah ◽  
Alexander Agung ◽  
Agus Arif
Keyword(s):  
Cycle Length ◽  
Polar Bear ◽  
Operating Time ◽  
Complex Problem ◽  
Fuel Loading ◽  
Loading Pattern ◽  
Maximum Value ◽  
Fuel Assemblies ◽  
The One ◽  
Optimum Solution

Abstract Fuel loading pattern optimization is a complex problem because there are so many possibilities for combinatorial solutions, and it will take time to try it one by one. Therefore, the Polar Bear Optimization Algorithm was applied to find an optimum PWR loading pattern based on BEAVRS. The desired new fuel loading pattern is the one that has the minimum Power Peaking Factor (PPF) value without compromising the operating time. Operating time is proportional to the multiplication factor (k eff ). These parameters are usually contradictive with each other and will make it hard to find the optimum solution. The reactor was modelled with the Standard Reactor Analysis Code (SRAC) 2006. Fuel pins and fuel assemblies are modelled with the PIJ module for cell calculations. One-fourth symmetry was used with the CITATION X-Y module for core calculations. The optimization was done with 200 populations and 50 iterations. The PPF value for the selected solution should never exceed 2.0 in every burn-up step. Out of 28 solutions, the best optimal fuel loading pattern had a maximum value PPF of 1.458 and a k eff of 0.916 at day 760 of calculated time (corresponding to a cycle length of 479 days). Therefore, the maximum PPF value was 27.1% lower than the safety factor, and the same operating time as the standard loading pattern has been achieved.

scholarly journals Application of Evolutionary Simulated Annealing Method to Design a Small 200 MWt Reactor Core

2021 ◽  
Vol 10 (4) ◽  
pp. 16-23
Author(s):  
Tran Viet Phu ◽  
Tran Hoai Nam ◽  
Hoang Van Khanh
Keyword(s):  
Simulated Annealing ◽  
Power Plant ◽  
Nuclear Power ◽  
Cycle Length ◽  
Reactor Core ◽  
Loading Pattern ◽  
The Core ◽  
Fuel Assemblies ◽  
Full Power ◽  
Annealing Method

This paper presents the application of an evolutionary simulated annealing (ESA) method to design a small 200 MWt reactor core. The core design is based on a reference ACPR50 reactor deployed in a floating nuclear power plant. The core consists of 37 typical 17x17 PWR fuel assemblies with three different U-235 enrichments of 4.45, 3.40 and 2.35 wt%. Core loading pattern (LP) has been optimized for obtaining the cycle length of 900 effective full power days, while minimizing the average U-235 enrichment and the radial power peaking factor. The optimization process was performed by coupling the ESA method with the COREBN module of the SRAC2006 system code.

scholarly journals Powering Down

2003 ◽  
Vol 125 (04) ◽  
pp. 46-48
Author(s):  
Harry Hutchinson
Keyword(s):  
Heat Transfer ◽  
Nuclear Reactor ◽  
Reactor Core ◽  
The United States ◽  
Nuclear Industry ◽  
Significant Feature ◽  
Pressurized Water ◽  
Safety Testing ◽  
Fuel Assemblies ◽  
Enriched Uranium

This article reviews that after a half century of safety testing for the nuclear industry, a key heat-transfer lab is losing its home. Columbia University’s Heat Transfer Research Facility has been the only place to go for key safety testing. Since the days of the Atoms for Peace program during the Eisenhower years, the lab has tested generations of nuclear reactor fuel assemblies. The lab’s clients over the years have included all the designers of pressurized water reactors in the United States and others from much of the world. The tests are primarily concerned with one small, but significant feature of a reactor core. A core contains as many as 3000 fuel assemblies, bundles of long, slender rods containing enriched uranium. Controlled fission among the bundles heats water to begin the series of heat-transfer cycles that send steam to the turbines that will drive generators.

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