The Effect of Pitch, Burnup, and Absorbers on a TRIGA Spent-Fuel Pool Criticality Safety

2003 ◽  
Vol 141 (2) ◽  
pp. 211-219 ◽  
Author(s):  
Marjan Logar ◽  
Robert Jeraj ◽  
Bogdan Glumac
Keyword(s):  
Spent Fuel ◽  
Spent Fuel Pool ◽  
Criticality Safety

scholarly journals Criticality safety analysis of spent fuel pool for a PWR using UO2, MOX, (Th-U)O2 and (TRU-Th)O2 fuels

2019 ◽  
Vol 7 (3A) ◽  
Author(s):  
Claubia Pereira ◽  
Jéssica P. Achilles ◽  
Fabiano Cardoso ◽  
Victor F. Castro ◽  
Maria Auxiliadora F. Veloso
Keyword(s):  
Normal Operation ◽  
Pressurized Water Reactor ◽  
Spent Fuel ◽  
Pressurized Water ◽  
Operation Conditions ◽  
Transport Code ◽  
Uranium Fuel ◽  
Fuel Assemblies ◽  
Spent Fuel Pool ◽  
Criticality Safety

A spent fuel pool of a typical Pressurized Water Reactor (PWR) was evaluated for criticality studies when it uses reprocessed fuels. PWR nuclear fuel assemblies with four types of fuels were considered: standard PWR fuel, MOX fuel, thorium-uranium fuel and reprocessed transuranic fuel spiked with thorium. The MOX and UO2 benchmark model was evaluated using SCALE 6.0 code with KENO-V transport code and then, adopted as a reference for other fuels compositions. The four fuel assemblies were submitted to irradiation at normal operation conditions. The burnup calculations were obtained using the TRITON sequence in the SCALE 6.0 code package. The fuel assemblies modeled use a benchmark 17x17 PWR fuel assembly dimensions. After irradiation, the fuels were inserted in the pool. The criticality safety limits were performed using the KENO-V transport code in the CSAS5 sequence. It was shown that mixing a quarter of reprocessed fuel withUO2 fuel in the pool, it would not need to be resized 

Criticality Safety Assessment of a TRIGA Reactor Spent-Fuel Pool Under Accident Conditions

1997 ◽  
Vol 117 (2) ◽  
pp. 248-254 ◽  
Author(s):  
Bogdan Glumac ◽  
Matjaž Ravnik ◽  
Marjan Logar
Keyword(s):  
Safety Assessment ◽  
Spent Fuel ◽  
Triga Reactor ◽  
Spent Fuel Pool ◽  
Accident Conditions ◽  
Criticality Safety

Validation of UNIST Monte Carlo code MCS for criticality safety analysis of PWR spent fuel pool and storage cask

2018 ◽  
Vol 114 ◽  
pp. 495-509 ◽  
Author(s):  
Jaerim Jang ◽  
Wonkyeong Kim ◽  
Sanggeol Jeong ◽  
Eun Jeong ◽  
Jinsu Park ◽  
...  
Keyword(s):  
Monte Carlo ◽  
Safety Analysis ◽  
Monte Carlo Code ◽  
Spent Fuel ◽  
Spent Fuel Pool ◽  
And Storage ◽  
Criticality Safety

scholarly journals INTRODUCING BURNUP CREDIT FOR EXPANSION STAGE 2 OF THE EXTERNAL SPENT FUEL POOL AT GÖSGEN NPP

2021 ◽  
Vol 247 ◽  
pp. 17007
Author(s):  
Axel Hoefer ◽  
Martin Basler ◽  
Oliver Buss ◽  
Gaëtan Girardin ◽  
Fabian Jatuff ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Multiplication Factor ◽  
Spent Fuel ◽  
Statistical Confidence ◽  
Fuel Assemblies ◽  
Neutron Multiplication ◽  
Expansion Stage ◽  
Spent Fuel Pool ◽  
Storage Racks ◽  
Criticality Safety

We present a summary of the actinide-plus-fission-product burnup credit criticality safety licensing analysis for Expansion Stage 2 (ES2) of the external spent fuel pool at Gösgen nuclear power plant. In ES2, the nine Expansion Stage 1 storage racks currently installed in the external spent fuel pool are going to be supplemented by nine ES2 storage racks with a significantly reduced fuel assembly pitch. They are designed for loadings with fuel assemblies above a well-defined minimum required burnup. The objective of the criticality safety analysis is to calculate the minimum required burnup values for the uranium and MOX fuel assemblies to be stored in the ES2 storage racks. We use a methodology that allows us to take into account the reactivity effects due to variabilities and uncertainties of all relevant parameters involved in a burnup credit criticality safety assessment in a bounding manner. These include manufacturing tolerances of the fuel assemblies and storage racks, the irradiation histories and burnup profiles of the spent fuel assemblies, the bias of the depletion code used to calculate the isotopic inventories of the irradiated fuel, and the bias of the criticality code used to calculate the neutron multiplication factor of the considered storage configuration. A combination of different statistical procedures is used to evaluate and propagate the uncertainty information on the input parameters and translate it into statistical confidence statements about the neutron multiplication factor. It should be noted that the presented analysis is related to the first implementation of a significant burnup credit for wet storage of PWR fuel in Switzerland.

scholarly journals Criticality safety analysis of spent fuel pool for TRIGA Puspati Reactor using MCNP5

2019 ◽  
Vol 555 ◽  
pp. 012001
Author(s):  
Nurlaila Syamsul Bahri ◽  
Jasman Zainal ◽  
Khaidzir Hamzah ◽  
Muneer Aziz Mohammad Saleh ◽  
Mohamad Hairie Rabir
Keyword(s):  
Safety Analysis ◽  
Spent Fuel ◽  
Spent Fuel Pool ◽  
Criticality Safety

The effect of eccentric loading in spent fuel pool criticality safety analyses

2018 ◽  
Vol 114 ◽  
pp. 407-412 ◽  
Author(s):  
Walid A. Metwally ◽  
Abdulrahman S. Alawad
Keyword(s):  
Spent Fuel ◽  
Spent Fuel Pool ◽  
Criticality Safety
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