STUDY ON TEMPERATURECOEFFICIENT OF REACTIVITY FOR PEBBLE BED REACTORWITH THORIUM FUEL

2019 ◽  
Author(s):  
Suwoto Suwoto ◽  
Wahid Luthfi ◽  
Hery Adrial ◽  
Zuhair
Keyword(s):  
Temperature Coefficient ◽  
Fuel Load ◽  
Positive Temperature ◽  
Pebble Bed ◽  
Pebble Bed Reactor ◽  
Fuel Cycles ◽  
Wide Range ◽  
Nuclear Data Library ◽  
Calculation Results ◽  
Coefficient Of Reactivity

The pebble bed reactor has a flexibility to utilize a wide range of different fuel cycles without significantly modifying the reactor core geometry. These fuel cycles can be comprised of various fissile and fertile fuel isotopes. The purpose of this paper is to study the temperature coefficient of reactivity for pebble bed reactor fuelled by thorium. The HTR-Modul was chosen as the reactor model. A series of calculations was performed by the use of the Monte Carlo transport code MCNP6 with the continuous energy nuclear data library ENDF/B-VII. The k∞ calculation results show that the fuel load with a mass of 2g Th/pebble, 5g Th/pebble and 20g Th/pebble can achieve a critical core with discharge burnup of 65,644; 101,500; and 114,215 MWd/t, respectively. The calculation results of temperature coefficient conclude that specific mass of thorium per pebble might have a positive temperature coefficient of reactivity at a certain temperature. Further investigation needs to be conducted to analyze the behavior of these temperature reactivity coefficients in more detail.

Performance of Thorium Fuel Cycles in the Pebble-Bed Reactor

1978 ◽  
Vol 38 (3) ◽  
pp. 374-383 ◽  
Author(s):  
Eberhard Teuchert ◽  
Hans Joachim Rütten ◽  
Heinz Werner
Keyword(s):  
Pebble Bed ◽  
Pebble Bed Reactor ◽  
Fuel Cycles

scholarly journals The effects of fuel type on control rod reactivity of pebble-bed reactor

Nukleonika ◽  
2019 ◽  
Vol 64 (4) ◽  
pp. 131-138
Author(s):  
◽  
Topan Setiadipura ◽  
Jim C. Kuijper ◽  
Keyword(s):  
Reactor Core ◽  
Fuel Type ◽  
Reactor Model ◽  
Pebble Bed ◽  
Pebble Bed Reactor ◽  
Control Rod ◽  
Reactor Geometry ◽  
Calculation Results ◽  
Control Rods ◽  
Selection Of

Abstract As a crucial core physics parameter, the control rod reactivity has to be predicted for the control and safety of the reactor. This paper studies the control rod reactivity calculation of the pebble-bed reactor with three scenarios of UO2, (Th,U)O2, and PuO2 fuel type without any modifications in the configuration of the reactor core. The reactor geometry of HTR-10 was selected for the reactor model. The entire calculation of control rod reactivity was done using the MCNP6 code with ENDF/B-VII library. The calculation results show that the total reactivity worth of control rods in UO2-, (U,Th)O2-, and PuO2-fueled cores is 15.87, 15.25, and 14.33%Δk/k, respectively. These results prove that the effectiveness of total control rod in thorium and uranium cores is almost similar to but higher than that in plutonium cores. The highest reactivity worth of individual control rod in uranium, thorium and plutonium cores is 1.64, 1.44, and 1.53%Δk/k corresponding to CR8, CR1, and CR5, respectively. The other results demonstrate that the reactor can be safely shutdown with the control rods combination of CR3+CR5+CR8+CR10, CR2+CR3+CR7+CR8, and CR1+CR3+CR6+CR8 in UO2-, (U,Th)O2-, and PuO2-fueled cores, respectively. It can be concluded that, even though the calculation results are not so much different, however, the selection of control rods should be considered in the pebble-bed core design with different scenarios of fuel type.

Self-Contained Intelligent Sensor-Actuator for Temperature Control

2002 ◽  
Author(s):  
A. M. Al-Jumaily ◽  
H. Kadhum
Keyword(s):  
Temperature Coefficient ◽  
Temperature Control ◽  
Conductive Polymer ◽  
Negative Temperature ◽  
Positive Temperature Coefficient ◽  
Positive Temperature ◽  
Intelligent Sensor ◽  
Conductive Composites ◽  
Sensor Actuator ◽  
Wide Range

Some electrically conductive polymer composites show positive temperature coefficient behavior during one temperature range followed by negative temperature coefficient behavior during the next range. The change normally occurs at a well-defined switching temperature. This paper proposes to use this phenomenon to develop an intelligent sensor-actuator device suited for temperature control applications. Two conductive composites were prepared and their switching temperatures were determined experimentally. Then a heated tube was made, with one of these composites as the heating element, and tested for the sensing-actuation control action. The results are very promising for future development of a wide range of such devices.

Core physics and fuel cycles of the pebble bed reactor

1975 ◽  
Vol 34 (1) ◽  
pp. 109-118 ◽  
Author(s):  
E. Teuchert ◽  
H.J. Rütten
Keyword(s):  
Pebble Bed ◽  
Pebble Bed Reactor ◽  
Fuel Cycles

scholarly journals Impact of Different Nuclear Data Library on Control Rod Reactivity Worth Calculation of Small Pebble Bed Reactor

2021 ◽  
Vol 2048 (1) ◽  
pp. 012029
Author(s):  
Suwoto ◽  
H Adrial ◽  
T Setiadipura ◽  
Zuhair ◽  
S Bakhri
Keyword(s):  
Nuclear Data ◽  
Pebble Bed ◽  
Integral Control ◽  
Pebble Bed Reactor ◽  
Control Rod ◽  
Nuclear Data Library ◽  
Data Libraries ◽  
And Control ◽  
Nuclear Data Libraries ◽  
Data Library

Abstract One of the main critical issues on a nuclear reactor is safety and control system. The control rod worth plays an important role in the safety and control of nuclear reactors. The control rods worth calculation is used to specify the safety margin of the reactor. The main objective of this work is to investigate impact of different nuclear data libraries on calculating the control rod reactivity worth on small pebble bed reactor. Calculation of the control rod reactivity worth in small high temperature gas cooled reactor has been conducted using the Monte Carlo N-Particle 6 (MCNP6) code coupled with a different nuclear data library. Famous evaluated nuclear data libraries such as JENDL-40u, ENDF/B-VII.1 and JEFF-3.2 continuous cross section-energy data libraries were used. The overall calculation results of integral control rod worth show that the ENDF/B-VII.1, JENDL-40u and JEFF-3.2 files give values of - 17.814%☐k/k, -18.0204 %☐k/k and -18.0267%☐k/k, respectively. Calculations using ENDF/B-VII.1 give a slightly lower value than the others, while the JENDL-4.0u file gives results that are close to JEFF-3.2 file. The different nuclear data libraries have a relatively small impact on the control rod worth of small pebble bed reactor. Accurate prediction by simulation of control rod worth is very important for the safety operation of all reactor types, especially for new reactor designs.

Proposal for an International Experimental Pebble Bed Reactor

2008 ◽  
Author(s):  
Dawid Serfontein ◽  
Eben Mulder ◽  
Eberhard Teuchert
Keyword(s):  
Carbon Fiber ◽  
Fuel Cycle ◽  
Heat Removal ◽  
Pebble Bed ◽  
Pebble Bed Reactor ◽  
Pebble Bed Reactors ◽  
Fuel Cycles ◽  
Short Time Span ◽  
Enriched Uranium ◽  
Vessel Development

HTRs, both prismatic block fuelled and pebble fuelled, feature a number of uniquely beneficial characteristics that will be discussed in this paper. In this paper the construction of an international experimental pebble bed reactor is proposed, possible experiments suggested and an invitation extended to interested partners for co-operation in the project. Experimental verification by nuclear regulators in order to facilitate licensing and the development of a new generation of reactors create a strong need for such a reactor. Suggested experiments include: • Optimized incineration of waste Pu in a pebble bed reactor: The capability to incineration pure reactor grade plutonium by means of ultra high burn-up in pebble bed reactors will be presented at this conference in the track on fuel and fuel cycles. This will enable incineration of the global stockpile of separated reactor grade Pu within a relatively short time span; • Testing of fuel sphere geometries, aimed at improving neutron moderation and a decrease in fuel temperatures; • Th/Pu fuel cycles: Previous HTR programs demonstrated the viability of a Th-232 fuel-cycle, using highly enriched uranium (HEU) as driver material. However, considerations favoring proliferation resistance limit the enrichment level of uranium in commercial reactors to 20%, thereby lowering the isotopic efficiency. Therefore, Pu driver material should be developed to replace the HEU component. Instead of deploying a (Th, Pu)O2 fuel concept, the proposal is to use the unique capability offered by pebble bed reactors in deploying separate Th- and Pu-containing pebbles, which can be cycled differently; • Testing of carbon-fiber-carbon (CFC) structures for in-core or near-core applications, such as guide tubes for reserve shutdown systems, thus creating the possibility to safely shutdown reactors with increased diameter; • Development of very high temperature reactor components for process heat applications; • Advanced decay heat removal systems e.g. design specific air flow channels, or heat pipe designs external to the reactor pressure vessel; • Development of a plutonium fuelled peaking reactor with the proposed duel cycle; • A radial coolant flow pattern with increased power output; • Testing of carbon-fiber-carbon (CFC) core barrel applications. The design will facilitate ease of licensing by sacrificing performance in favor of safety and employing redundant defense-in-depth safety systems. Speedy licensing is therefore expected. The economic model will be based on a commercial expedition of the agreed experimental value to collaborating participants. Target costs will be minimized by exploiting known technology only and by utilizing off-the-shelf components as far as possible.

Preliminary neutronic study on Pu-based OTTO cycle pebble bed reactor

Kerntechnik ◽  
2017 ◽  
Vol 82 (6) ◽  
pp. 643-647 ◽  
Author(s):  
T. Setiadipura ◽  
D. Irwanto ◽  
Zuhair
Keyword(s):  
Otto Cycle ◽  
Pebble Bed ◽  
Pebble Bed Reactor
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