Multi purpose research reactor

Raina, V. K.; Sasidharan, K.; Sengupta, S.; Singh, Tej

doi:10.1016/j.nucengdes.2005.09.022

Cited by 10 publications

(11 citation statements)

References 2 publications

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“…They have different temperatures at various seasons. The second problem is that some details of reactor thermohydraulic quantities or heat structure data are not available from Indian reactor (Raina et al, 2006). Therefore standard values from reference books (Valves, Piping & Pipelines in Handbook (1996);ElWakil, 1971) are used.…”

Section: Steady State Results and Comparisonmentioning

confidence: 99%

“…The reactor will be fueled with Low Enriched Uranium dispersion type fuel and will use light water as coolant and moderator. The reactor core will be surrounded by an annular heavy water tank to achieve a high neutron flux and irradiation volume to maximize the number of irradiation positions available for isotope production and material irradiation (Raina et al, 2006).…”

Section: Introductionmentioning

confidence: 99%

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Loss of coolant accident analyses on multi purpose research reactor by RELAP5/MOD3.2 code

Karimpour

Esteki

2015

Progress in Nuclear Energy

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Section: Steady State Results and Comparisonmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Loss of coolant accident analyses on multi purpose research reactor by RELAP5/MOD3.2 code

Karimpour

Esteki

2015

Progress in Nuclear Energy

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“…Breakaway swelling is typically associated with (Tukiran S) changes in the fuel microstructure, leading to sudden increased mobility for fission gas. For the UMoAl dispersion fuel system with atomized U-7w%Mo dispersed at a loading of ~8gU/cc, the observations are that plate pillowing occurs at relatively low burn-up (30-40%), where the plate thickness increases with fission density accumulation [7]. The different power levels, plates were found to pillow at local burn-up of 35-40% [7].…”

Section: Introductionmentioning

confidence: 95%

“…For the UMoAl dispersion fuel system with atomized U-7w%Mo dispersed at a loading of ~8gU/cc, the observations are that plate pillowing occurs at relatively low burn-up (30-40%), where the plate thickness increases with fission density accumulation [7]. The different power levels, plates were found to pillow at local burn-up of 35-40% [7]. Also in the case of the IRIS-3 plates with very low Si content (0.3%) in the matrix, the burn-up at which pillowing was observed were very similar [8].…”

Section: Introductionmentioning

confidence: 99%

“…Normal solid state fuel swelling under the influence of the incorporation of fission product, particularly the high yield Xe atoms, is inevitable. The amount of swelling that can be tolerated depends on the design, but should preferably not exceed 150-200 µm [7]. In addition to remaining limited, the swelling should also be controlled and be a gradual function of burn-up as uncontrolled accelerations in the swelling rate are not acceptable.…”

Section: Introductionmentioning

confidence: 99%

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Neutronics Analysis on Mini Test Fuel in the RSG-Gas Core

Surbakti

Sembiring

2016

Tri Dasa Mega

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NEUTRONICS ANALYSIS ON MINI TEST FUEL IN THE RSG-GAS CORE.Research on UMo fuel for research reactor has been developed. The fuel of research reactor is uranium molybdenum low enrichment with high density. For supporting the development of fuel fabrication, an neutronic analysis of mini fuel plates in the RSG-GAS core was performed. The aim of analysis is to determine the numbers of fuel cycles in the core to know the maximum fuel burn-up. The mini fuel plates of U7Mo-Al and U6Zr-Al with densities of 7.0 gU/cc and 5.2 gU/cc, respectively, will be irradiated in the RSG-GAS core. The size of both fuels, namely 630x70.75x1.30 mm were inserted to the 3 plates of dummy fuel. Before the fuel will be irradiated in the core, a calculation for safety analysis from neutronics and thermal-hydraulics aspects were required. However, in this paper, it will be discussed safety analysis of the U7Mo-Al and U6Zr-Al mini fuels from neutronic point of view. The calculation was done using WIMSD-5B and Batan-3DIFF codes. The result showed that both of the mini fuels could be irradiated in the RSG-GAS core with burn up less than 70 % within 12 cycles of operation without over limiting the safety margin. If it is compared, the power density of U7Mo-Al mini fuel is bigger than U6Zr-Al fuel.Key words: mini fuel, neutronics analysis, reactor core, safety analysis ABSTRAK ANALISIS NEUTRONIK ELEMEN BAKAR UJI MINI DI TERAS RSG-GAS. Penelitian tentang bahan bakar UMo untuk reaktor riset terus berkembang saat ini. Bahan bakar reaktor riset yang digunakan adalah uranium pengkayaan rendah namun densitas tinggi. Untuk mendukung pengembangan bahan bakar dilakukan uji elemen bakar mini di teras reaktor RSG-GAS dengan tujuan menentukan jumlah siklus di dalam teras sehingga tercapai fraksi bakar maksimum. Bahan bakar yang diuji adalah

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An algorithm for accurate modeling and simulating reactor cores with involute‐shaped fuel plates by Monte Carlo

et al. 2021

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Summary A real three‐dimensional representation of reactor core with involute fuel plates via Monte Carlo method is still lacking at the present, and usually equivalent homogeneous models of water coolants and simplified fuel plate shapes have been used. This work proposed an algorithm to simulate the reactor core composed of involute fuel plates with an explicit accurate description of its involute surfaces. The description of involute surfaces is through its governing equations. The mathematical function methods to depict the involute curves and the schemes to compute the distance between any neutron particle and an involute surface along a ray are presented and demonstrated step‐by‐step. The algorithm is realized in the Monte Carlo code and validated by the published data of a high flux isotope reactor. This study definitively provides a method to model the involute fuel plates in the Monte Carlo simulation.

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Multi purpose research reactor

Cited by 10 publications

References 2 publications

Loss of coolant accident analyses on multi purpose research reactor by RELAP5/MOD3.2 code

Loss of coolant accident analyses on multi purpose research reactor by RELAP5/MOD3.2 code

Neutronics Analysis on Mini Test Fuel in the RSG-Gas Core

An algorithm for accurate modeling and simulating reactor cores with involute‐shaped fuel plates by Monte Carlo

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