scholarly journals Supplement to safety analysis report for packaging steel banded wooden shipping containers for slightly enriched uranium metal (NLCO-1107). [NLO containers]

1979 ◽  
Author(s):  
D. L. Honkonen
Keyword(s):  
Safety Analysis ◽  
Uranium Metal ◽  
Shipping Containers ◽  
Enriched Uranium

scholarly journals Review of accident analyses of RB experimental reactor

2003 ◽  
Vol 18 (1) ◽  
pp. 3-15
Author(s):  
Milan Pesic
Keyword(s):  
Aluminum Matrix ◽  
Safety Analysis ◽  
Natural Uranium ◽  
Regulatory Body ◽  
Uranium Metal ◽  
Technical Modifications ◽  
Metal Fuel ◽  
Enriched Uranium ◽  
Safety Systems ◽  
Fuel Elements

The RB reactor is a uranium fuel heavy water moderated critical assembly that has been put and kept in operation by the VTNCA Institute of Nuclear Sciences, Belgrade, Serbia and Montenegro, since April 1958. The first complete Safety Analysis Report of the RB reactor was prepared in 1961/62 yet, the first accident analysis had been made in late 1958 with the aim to examine a power transition and the total equivalent doses received by the staff during the reactivity accident that occurred on October 15, 1958. Since 1960, the RB reactor has been modified a few times. Beside the initial natural uranium metal fuel rods, new types of fuel (TVR-S types of Russian origin) consisting of 2% enriched uranium metal and 80% enriched UO2 dispersed in aluminum matrix, have been available since 1962 and 1976 respectively. Modifications of the control and safety systems of the reactor were made occasionally. Special reactor cores were designed and constructed using all three types of fuel elements as well as the coupled fast-thermal ones. The Nuclear Safety Committee of the VINCA Institute, an independent regulatory body, approved for usage all these modifications of the RB reactor on the basis of the Preliminary Safety Analysis Reports, which, beside proposed technical modifications and new regulation rules, included safety analyses of various possible accidents. A special attention was given (and a new safety methodology was proposed) to thorough analyses of the design-based accidents related to the coupled fast-thermal cores that included central zones of the reactor filled by the fuel elements without any moderator. In this paper, an overview of some accidents, methodologies and computation tools used for the accident analyses of the RB reactor is given.

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.

Prompt-Neutron Lifetime in Critical Enriched-Uranium Metal Cylinders and Annuli

1964 ◽  
Vol 20 (1) ◽  
pp. 60-65 ◽  
Author(s):  
John T. Mihalczo
Keyword(s):  
Prompt Neutron ◽  
Neutron Lifetime ◽  
Uranium Metal ◽  
Enriched Uranium

scholarly journals ENRICHED URANIUM-METAL MEASUREMENTS, NO. 1.

1967 ◽  
Author(s):  
G. Tuck
Keyword(s):  
Uranium Metal ◽  
Enriched Uranium

Critical Mass Irregularity of Steel-Moderated Enriched Uranium Metal Assemblies with Composite Steel-Oil Reflectors

1970 ◽  
Vol 39 (3) ◽  
pp. 320-328 ◽  
Author(s):  
Donald C. Coonfield ◽  
Grover Tuck ◽  
Harold E. Clark ◽  
Bruce B. Ernst
Keyword(s):  
Critical Mass ◽  
Uranium Metal ◽  
Enriched Uranium ◽  
Composite Steel

Reactor Physics Parameters of 1.03% Enriched Uranium Metal, D2O Moderated Lattices

1968 ◽  
Vol 32 (3) ◽  
pp. 283-291 ◽  
Author(s):  
Walter H. D’Ardenne ◽  
Henry E. Bliss ◽  
David D. Lanning ◽  
Irving Kaplan ◽  
Theos J. Thompson
Keyword(s):  
Reactor Physics ◽  
Uranium Metal ◽  
Enriched Uranium

Manufacturing low enriched uranium metal by magnesiothermic reduction of UF4

2017 ◽  
Vol 110 ◽  
pp. 874-885 ◽  
Author(s):  
M. Durazzo ◽  
A.M. Saliba-Silva ◽  
I.C. Martins ◽  
E.F. Urano de Carvalho ◽  
H.G. Riella
Keyword(s):  
Magnesiothermic Reduction ◽  
Uranium Metal ◽  
Enriched Uranium

scholarly journals CRITICAL MASSES OF STEEL-MODERATED, ENRICHED URANIUM METAL ASSEMBLIES WITH COMPOSITE STEEL--OIL REFLECTORS.

1967 ◽  
Author(s):  
D.C. Coonfield ◽  
G. Tuck ◽  
H.E. Clark ◽  
B.B. Ernst
Keyword(s):  
Uranium Metal ◽  
Enriched Uranium ◽  
Composite Steel
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