Validation and Extension of a Correlation for Predicting Onset of Nucleate Boiling in Plate-Type Research Reactors

1992 ◽  
Vol 98 (3) ◽  
pp. 333-348 ◽  
Author(s):  
Efigenio Cubillos-Moreno ◽  
Mohamed Belhadj ◽  
Tunc Aldemir
Keyword(s):  
Nucleate Boiling ◽  
Research Reactors ◽  
Plate Type

scholarly journals Thermal-hydraulic Fortran program for steady-state calculations of plate-type fuel research reactors

2008 ◽  
Vol 23 (1) ◽  
pp. 19-30 ◽  
Author(s):  
Ahmed Khedr
Keyword(s):  
Steady State ◽  
Flow Instability ◽  
Continuous Process ◽  
Nucleate Boiling ◽  
Fortran Program ◽  
Coolant Temperature ◽  
Regulatory Body ◽  
Research Reactors ◽  
Type Fuel ◽  
Plate Type

The safety assessment of research and power reactors is a continuous process covering their lifespan and requiring verified and validated codes. Power reactor codes all over the world are well established and qualified against real measuring data and qualified experimental facilities. These codes are usually sophisticated, require special skills and consume a lot of running time. On the other hand, most research reactor codes still require much more data for validation and qualification. It is, therefore, of benefit to any regulatory body to develop its own codes for the review and assessment of research reactors. The present paper introduces a simple, one-dimensional Fortran program called THDSN for steady-state thermal-hydraulic calculations of plate-type fuel research reactors. Besides calculating the fuel and coolant temperature distributions and pressure gradients in an average and hot channel, the program calculates the safety limits and margins against the critical phenomena encountered in research reactors, such as the onset of nucleate boiling, critical heat flux and flow instability. Well known thermal-hydraulic correlations for calculating the safety parameters and several formulas for the heat transfer coefficient have been used. The THDSN program was verified by comparing its results for 2 and 10 MW benchmark reactors with those published in IAEA publications and a good agreement was found. Also, the results of the program are compared with those published for other programs, such as the PARET and TERMIC.

scholarly journals Studies on Production Planning of Dispersion Type U<sub>3</sub>Si<sub>2</sub>-Al Fuel in Plate-Type Fuel Elements for Nuclear Research Reactors

2016 ◽  
Vol 06 (04) ◽  
pp. 217-231
Author(s):  
Miguel Luiz Miotto Negro ◽  
Michelangelo Durazzo ◽  
Marco Aurélio de Mesquita ◽  
Elita Fontenele Urano de Carvalho ◽  
Delvonei Alves de Andrade
Keyword(s):  
Production Planning ◽  
Nuclear Research ◽  
Research Reactors ◽  
Fuel Elements ◽  
Type Fuel ◽  
Plate Type

Transient Behavior of Low Enriched Uranium Silicide Plate-Type Fuel for Research Reactors during Reactivity Initiated Accident Conditions

1993 ◽  
Vol 30 (8) ◽  
pp. 741-751 ◽  
Author(s):  
Kazuaki YANAGISAWA ◽  
Toshio FUJURO ◽  
Oichiro HORIKI ◽  
Kazuhiko SOYAMA ◽  
Hiroki ICHIKAWA ◽  
...  
Keyword(s):  
Transient Behavior ◽  
Research Reactors ◽  
Enriched Uranium ◽  
Accident Conditions ◽  
Type Fuel ◽  
Plate Type ◽  
Uranium Silicide

Nondestructive evaluation of plate type nuclear fuel elements for PURNIMA-III and KAMINI research reactors

1992 ◽  
pp. 130-137
Author(s):  
J.K. Ghosh ◽  
S. Muralidhar ◽  
K.N. Chandrasekharan ◽  
V.D. Pandey ◽  
A. Subramanian ◽  
...  
Keyword(s):  
Nondestructive Evaluation ◽  
Nuclear Fuel ◽  
Research Reactors ◽  
Fuel Elements ◽  
Plate Type

Steady state thermal hydraulic calculations for MTR plate-type research reactors

Kerntechnik ◽  
2010 ◽  
Vol 75 (3) ◽  
pp. 97-102
Author(s):  
I. D. Abdelrazek ◽  
W. I. Zidan ◽  
A. M. Shokr ◽  
M. A. Gaheen
Keyword(s):  
Steady State ◽  
Research Reactors ◽  
Plate Type

Cooling capacity of plate type research reactors during the natural convective cooling mode

2012 ◽  
Vol 56 ◽  
pp. 37-42 ◽  
Author(s):  
Daeseong Jo ◽  
Suki Park ◽  
Jonghark Park ◽  
Heetaek Chae ◽  
Byungchul Lee
Keyword(s):  
Cooling Capacity ◽  
Cooling Mode ◽  
Convective Cooling ◽  
Research Reactors ◽  
Plate Type

scholarly journals ANALISIS KONVEKSI ALAM TERAS REAKTOR TRIGA BERBAHAN BAKAR TIPE PELAT MENGGUNAKAN COOLOD-N2

2015 ◽  
Vol 17 (2) ◽  
pp. 67 ◽  
Author(s):  
Sudjatmi K A ◽  
Endiah Puji Hastuti ◽  
Surip Widodo ◽  
Reinaldy Nazar
Keyword(s):  
Natural Convection ◽  
Fuel Element ◽  
Flow Instability ◽  
Reactor Core ◽  
Nucleate Boiling ◽  
Coolant Temperature ◽  
Triga Reactor ◽  
Fuel Elements ◽  
Type Fuel ◽  
Plate Type

ABSTRAK Analisis Konveksi Alam Teras Reaktor Triga Berbahan Bakar Tipe Pelat MENGGUNAKAN COOLOD-N2. Rencana penghentian produksi elemen bakar jenis TRIGA oleh produsen elemen bakar reaktor TRIGA, sudah seharusnya diantisipasi oleh badan pengoperasi reaktor TRIGA untuk menggantikan elemen bakar tipe silinder tersebut dengan tipe pelat yang tersedia di pasaran. Pada penelitian ini dilakukan perhitungan untuk model teras reaktor dengan spesifikasi utama menggunakan bahan bakar U3Si2Al dengan pengayaan uranium  sebesar 19,75% dan tingkat muat 2,96 gU/cm3. Analisis dilakukan menggunakan program COOLOD-N2 yang tervalidasi pada konfigurasi teras TRIGA konversi berbahan bakar tipe pelat, yang tersusun atas 16 elemen bakar, 4 elemen kendali dan 1 fasilitas iradiasi yang terletak tepat di tengah teras. Hasil analisis menunjukkan bahwa dengan temperatur pendingin masuk ke teras sebesar 37oC, dan rasio faktor puncak daya radial ≤ 1,92 maka daya maksimum yang dapat dioperasikan pada moda operasi konveksi bebas adalah 600 kW. Karakteristik termohidrolika yang diperoleh antara lain adalah temperatur pendingin di sisi outlet, kelongsong dan meat masing-masing sebesar 82,39oC, 108,88oC, dan 109,02oC, pada ΔTONB (Temperature Onset of Nucleate Boiling) =7,18oC dan nilai OFIR (Onset of flow instability ratio) =1,03 Hasil yang diperoleh dari perhitungan ini diharapkan dapat dijadikan acuan untuk menentukan tingkat daya reaktor TRIGA berbahan bakar pelat. Kata kunci: TRIGA Konversi, COOLOD-N2, karakteristik termohidrolika, konveksi alam, elemen bakar tipe pelat.  ABSTRACT ANALYSIS OF NATURAL CONVECTION IN TRIGA REACTOR CORE PLATE TYPES FUELED USING COOLOD-N2. Any pretensions to stop the production of TRIGA fuel elements by TRIGA reactor fuel elements manufacturer should be anticipated by the operating agency of TRIGA reactor to replace the cylinder type fuel element with plate type fuel element that available on the market. In this study, the calculation of U3Si2Al fuel with uranium enrichment of 19.75 % and a load level of 2.96 gU/cm3 was performed. Analyses were performed using the validated COOLOD - N2 program. TRIGA conversion core configurations of fuel plate type are composed of 16 fuel elements, 4 control elements and 1 irradiation facilities which are located in the middle of core. The calculation results showed that if the cooling temperature was 37°C, and the ratio of radial power peaking factor ≤ 1.92, then the maximum power that can be operated on free convection mode of operation was 600 kW. The thermalhydraulic characteristic obtained such as coolant temperature at the outlet side, cladding and meat were 82.39°C, 108.88°C and 109.02°C respectively, while the ΔTONB (Temperature Onset of Nucleate Boiling) was 7.18°C and OFIR (Onset of flow instability ratio) value was 1.03. The results are expected to be used as a reference for determining the power level of the TRIGA reactor core plate types fueled. Keywords: TRIGA Convertion, COOLOD-N2, Thermalhydraulics characteristic, natural convection, plate type fuel element.

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