scholarly journals CRITICALITY SAFETY ANALYSIS REPORT: HANDLING AND STORAGE OF ENRICHED URANIUM TO 1.25 WEIGHT PERCENT IN DUN FACILITIES 313 AND 3712 BUILDINGS.

1972 ◽  
Author(s):  
R. R. Stickney
Keyword(s):  
Safety Analysis ◽  
Weight Percent ◽  
Enriched Uranium ◽  
And Storage ◽  
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

Steady-State Safety Analysis of Ghana Research Reactor-1 With Low-Enriched-Uranium Core

2020 ◽  
Vol 12 (5) ◽  
Author(s):  
Edward Shitsi ◽  
Prince Amoah ◽  
Emmanuel Ampomah-Amoako ◽  
Henry Cecil Odoi
Keyword(s):  
Steady State ◽  
Research Reactor ◽  
Flow Instability ◽  
Argonne National Laboratory ◽  
Safety Analysis ◽  
Nucleate Boiling ◽  
Pressurized Water ◽  
Safety Margins ◽  
Water Reactors ◽  
Enriched Uranium

Abstract Research reactors all over the world are expected to operate within certain safety margins just like pressurized water reactors and boiling water reactors. These safety margins mainly include onset of nucleate boiling ratio (ONBR), departure from nucleate boiling ratio (DNBR), and flow instability ratio (FIR) in addition to the maximum clad or fuel temperature and saturation temperature or boing point of the coolant inside the core of the reactor. This study carried out steady-state safety analysis of the Ghana Research Reactor-1 (GHARR-1) with low enriched uranium (LEU) core. Monte Carlo N-particle (MCNP) code was used to obtain radial and axial power peaking factors used as inputs in the preparation of the input file of plate temperature code of Argonne National Laboratory (PLTEMP/ANL code), which was then used to obtain the mentioned safety parameters of GHARR-1 with LEU core in this study. The data obtained on the ONBR were used to obtain the initiation of nucleate boiling boundary data with respect to the active length of the reactor core for various reactor powers. The obtained results for LEU core were also compared with that of the high enriched uranium (HEU) core. The results obtained show that the 34 kW GHARR-1 with LEU core is safe to operate just as the previous 30 kW HEU core was safe to operate.

A study of burnup credit in criticality safety analysis for PBR spent fuel pebbles

2019 ◽  
Vol 132 ◽  
pp. 347-356 ◽  
Author(s):  
Shang-Chien Wu ◽  
Der-Sheng Chao ◽  
Jenq-Horng Liang
Keyword(s):  
Safety Analysis ◽  
Spent Fuel ◽  
Criticality Safety

Criticality safety analysis for a core catcher designed in Korea

2012 ◽  
Vol 59 ◽  
pp. 66-74 ◽  
Author(s):  
Song Hyun Kim ◽  
Chang Ho Shin ◽  
Hong-Chul Kim ◽  
Jong Kyung Kim ◽  
Jin Ho Song ◽  
...  
Keyword(s):  
Safety Analysis ◽  
Core Catcher ◽  
Criticality Safety
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