Relevant bibliographies by topics / Reactivity Worth

Contents

  1. Journal articles
  2. Dissertations / Theses
  3. Book chapters
  4. Conference papers
  5. Reports

Academic literature on the topic 'Reactivity Worth'

Author: Grafiati
Published: 4 June 2021
Last updated: 12 February 2022

Create a spot-on reference in APA, MLA, Chicago, Harvard, and other styles

Select a source type:

Consult the lists of relevant articles, books, theses, conference reports, and other scholarly sources on the topic 'Reactivity Worth.'

Next to every source in the list of references, there is an 'Add to bibliography' button. Press on it, and we will generate automatically the bibliographic reference to the chosen work in the citation style you need: APA, MLA, Harvard, Chicago, Vancouver, etc.

You can also download the full text of the academic publication as pdf and read online its abstract whenever available in the metadata.

Journal articles on the topic "Reactivity Worth"

1

Shen, Dan, and Massimiliano Fratoni. "BENCHMARK EVALUATION OF REACTIVITY EFFECTS AND REACTIVITY COEFFICIENTS IN THE MOLTEN SALT REACTOR EXPERIMENT." EPJ Web of Conferences 247 (2021): 06043. http://dx.doi.org/10.1051/epjconf/202124706043.

Full text
Abstract:
A set of benchmarks based on the experimental data from the Molten Salt Reactor Experiment (MSRE) is being compiled as part of International Reactor Physics Experiments Evaluation Reactor Physics Experiments Evaluation Project (IRPhEP). The initial benchmark that will be available in the 2019 edition of the IRPhEP handbook covers the first zero-power criticality experiment. Follow up benchmarks are under development based on the series of control rod calibration experiments performed at the MSRE, which consisted in progressive addition of a small amount (85g) of 235U in the salt followed by the insertion of the control rods acts to compensate for the excess reactivity insertion. Multiple reactivity effects and coefficients measurements are included in the benchmark: differential worth of a control rod, reactivity equivalent of 235U addition, control rod bank worth, reactivity effect of fuel circulation, isothermal temperature coefficient and fuel temperature coefficient. An uncertainty of 2% is attributed to the reported reactivity measurements from experimenters and it was believed that the uncertainty of reactor period measurement contributed the most of the experimental uncertainty. An additional 2% uncertainty was added to all reactivity measurements to represent the uncertainty for the correction factor applied to pull all the measurements on the same uranium concentration and this uncertainty was reasonably inferred by evaluating this factor on the MSRE benchmark model. The calculated reactivity equivalent of 235U additions (0.2228±0.0014, represented as the change of reactivity over the relative change of 235U mass in loop) matches well with the experiment value (0.223±0.006). Most of other calculations, including the control rod bank worth, reactivity effects of fuel circulation and isothermal and fuel temperature coefficients fall within one standard deviation from the experimental values as well.
APA, Harvard, Vancouver, ISO, and other styles
2

Hosan, Md Iqbal, MAM Soner, Md Fazlul Huq, and Khorshed Ahmad Kabir. "Measurement and Comparison of Control Rod Worth of BTRR using Inhour Equation and Period reactivity conversion table." Journal of Bangladesh Academy of Sciences 41, no. 1 (August 23, 2017): 95–103. http://dx.doi.org/10.3329/jbas.v41i1.33507.

Full text
Abstract:
In a nuclear reactor, control rod is a very essential part and plays the elementary role in the reactor control during reactor start up, normal power operation, experimental research and shutdown. To perform all these operations safely, knowledge of differential and integral worth of the control rod is mandatory. In this study, the differential and integral worth curve of all control rods of BAEC TRIGA Research Reactor (BTRR) have been determined by using the positive period method. Reactor period was measured from 1.5 folding time, doubling time, 5 folding time respectively; and in the above three cases reactivity has also been calculated from INHOUR equation and period reactivity conversion table. The total worth of all control rods of BTRR are measured as 14.888 $, 14.672 $, 14.348 $ from INHOUR equation and 13.978 $, 13.672 $, 13.357 $ from period reactivity conversion table for 1.5 folding time, doubling time and 5 folding time respectively. The measured reactivity has also been compared with the previously measured reactivity and due to fuel burn up of the reactor expected lower values were observed.Journal of Bangladesh Academy of Sciences, Vol. 41, No. 1, 95-103, 2017
APA, Harvard, Vancouver, ISO, and other styles
3

Jiang, Wei, Long Gu, Lu Zhang, Qi Zhou, Liang Chen, Jin-Yang Li, Rui Yu, Qing-Fu Zhu, and Yong Dai. "Validation of Neutron Evaluated Data Based on The Experimental Reactivity Worth of Tungsten Target in CiADS." EPJ Web of Conferences 225 (2020): 04026. http://dx.doi.org/10.1051/epjconf/202022504026.

Full text
Abstract:
Measurement of a cylindrical tungsten target reactivity worth has been performed on the light water zero-power reactor of VENUS-II at China Institute of Atomic Energy (CIAE) in order to verify the neutron evaluated data related to the engineering design of Chinese initiative Accelerator Driven Systems (CiADS). The reactivity worth of the tungsten target was measured and processed as -1.234±0.114mk by a period method. The experimental result was compared with the simulation ones calculated by MCNP with five different libraries, i.e., ENDF/B-VII.0, ENDF/B-VII.1, JENDL-4.0, CENDL-3.1 and JEFF-3.2. By comparing the results of experiment and simulation, the simulated results from ENDF/B-VII.0, JENDL-4.0 and JEFF-3.2 are higher than the experimental result, however that from CENDL-3.1 is lower. The result from ENDF/B-VII.1 library shows better agreement with the experiment one and the relative deviation is less than 2%. Through the analysis of the differences of the results, non-tungsten elements cross sections in the ENDF/B-VII.1 mainly affect the tungsten radiation capture and elastic scattering reaction rates in the energy range of 10-9-10-7 MeV, which results in a better simulated tungsten target reactivity worth value. Therefore, it is recommended that the tungsten target reactivity worth should be calculated with the ENDF/B-VII.1.
APA, Harvard, Vancouver, ISO, and other styles
4

Wenz, Tracy R., and Robert D. Busch. "Modeling of Central Reactivity Worth Measurements in Lady Godiva." Nuclear Technology 105, no. 1 (January 1994): 31–36. http://dx.doi.org/10.13182/nt94-a34908.

Full text
APA, Harvard, Vancouver, ISO, and other styles
5

Balakrishnan, Kamala, Umasankari Kannan, and Anil Kakodkar. "Reactivity worth of liquid poison jets in the moderator." Annals of Nuclear Energy 20, no. 6 (June 1993): 391–405. http://dx.doi.org/10.1016/0306-4549(93)90065-w.

Full text
APA, Harvard, Vancouver, ISO, and other styles
6

NAGAYA, Yasunobu, and Takamasa MORI. "Estimation of Sample Reactivity Worth with Differential Operator Sampling Method." Progress in Nuclear Science and Technology 2 (October 1, 2011): 842–50. http://dx.doi.org/10.15669/pnst.2.842.

Full text
APA, Harvard, Vancouver, ISO, and other styles
7

Shahbunder, Hesham I., Esmat H. Amin, Samir U. El-Khameesy, and Noura H. Hafez. "MCNPX calculation of the reactivity worth of actinides OSMOSE samples." Annals of Nuclear Energy 80 (June 2015): 70–76. http://dx.doi.org/10.1016/j.anucene.2015.01.031.

Full text
APA, Harvard, Vancouver, ISO, and other styles
8

Minhat, Mohd Sabri, Nurul Adilla Mohd Subha, Fazilah Hassan, and Norjulia Mohamad Nordin. "An improved control rod selection algorithm for core power control at TRIGA PUSPATI Reactor." Journal of Mechanical Engineering and Sciences 14, no. 1 (March 23, 2020): 6362–79. http://dx.doi.org/10.15282/jmes.14.1.2020.13.0498.

Full text
Abstract:
The 1 MWth TRIGA PUSPATI Reactor known as RTP undergoes more than 37 years of operation in Malaysia. The current core power control utilized Feedback Control Algorithm (FCA) and a conventional Control Rod Selection Algorithm (CRSA). However, the current power tracking performance suffers and increase the workload on Control Rod Drive Mechanism (CRDM) if the range between minimum and maximum rod worth value for each control rod has a significant difference. Thus, it is requiring much time to keep the core power stable at the power demand value within the acceptable error bands for the safety requirement of the RTP. In conventional CRSA, regardless of the rod worth value, the lowest position of the control rod is selected for up-movement to regulate the reactor power with 2% chattering error. To improve this method, a new CRSA is introduced named Single Control Absorbing Rod (SCAR). In SCAR, only one rod with highest reactivity worth value will be selected for coast tuning during transient and the lowest reactivity worth value will be selected for fine-tuning rod movement during steady-state. The simulation model of the reactor core is represented based on point kinetics model, thermal-hydraulic models and reactivity model. The conventional CRSA model included with control rod position dynamic model and actual reactivity worth curve data from RTP. The FCA controller is designed based on Proportional-Integral (PI) controller using MATLAB Simulink simulation. The core power control system is represented by the integration of a reactor core model, CRSA model and FCA controller. To manifest the effectiveness of the proposed SCAR algorithm, the results are compared to the conventional CRSA in both simulation and experimentation. Overall, the results shows that the SCAR algorithm offers generally better results than the conventional CRSA with the reduction in rising time up to 44%, workload up to 35%, settling time up to 26% and chattering error up to 18% of the nominal value.
APA, Harvard, Vancouver, ISO, and other styles
9

Šalamon, L., B. Geslot, J. Heyse, S. Kopecky, P. Leconte, G. Noguere, C. Paradela, P. Schillebeeckx, and L. Snoj. "Neutron resonance transmission analysis of cylindrical samples used for reactivity worth measurements." EPJ Web of Conferences 239 (2020): 01022. http://dx.doi.org/10.1051/epjconf/202023901022.

Full text
Abstract:
A characterisation of cylindrical samples by Neutron Resonance Transmission Analysis (NRTA) at the GELINA facility of JRC Geel (Belgium) is presented. The samples were designed and produced for reactivity worth measurements in the MINERVE reactor of CEA Cadarache (France). NRTA was applied to determine the nuclide composition of UO2, Al2O3 and liquid samples that were doped with silver. The volume number densities of 238U, 107Ag and 109Ag obtained by NRTA are within 2 % fully consistent with the values that are quoted by the manufacturer. In addition, the NRTA data reveal a tungsten contamination which is not reported by the provider. It is shown that such a contamination contributes by up to 5.7 % to the reactivity worth.
APA, Harvard, Vancouver, ISO, and other styles
10

Hassan, Md Mehedi, K. M. Jalal Uddin Rumi, Md Nazrul Islam Khan, and Rajib Goswami. "Estimation of control rod worth, xenon effect on reactivity and power defect of BAEC TRIGA Mark-II research reactor." Modern Physics Letters A 33, no. 39 (December 21, 2018): 1850233. http://dx.doi.org/10.1142/s0217732318502334.

Full text
Abstract:
In this work, control rod worth, xenon (Xe) effect on reactivity and power defect have been measured by doing experiments in the BAEC TRIGA Mark-II research reactor (BTRR) and through established theoretical analysis. Firstly, to study the xenon-135 effect on reactivity, reactor is critical at 2.4 MW for several hours. Next, experiments have been performed at very low power (50 W) to avoid temperature effects. Moreover, for the power defect experiment, different increasing power level has been tested by withdrawing the control rods. Finally, it is concluded that the total control rods worth of the BAEC TRIGA Mark-II research reactor, as determined through this study, is enough to run the reactor at full power (3 MW) considering the xenon-135 and fuel temperature effects.
APA, Harvard, Vancouver, ISO, and other styles
More sources

Dissertations / Theses on the topic "Reactivity Worth"

1

Ma, Zhegang. "Development of MURR flux trap model for simulation and prediction of sample loading reactivity worth and isotope production." Diss., Columbia, Mo. : University of Missouri-Columbia, 2007. http://edt.missouri.edu/Winter2007/Dissertation/MaZ-050807-D7038/.

Full text
Abstract:
Thesis (Ph. D.)--University of Missouri-Columbia, 2007.
The entire dissertation/thesis text is included in the research.pdf file; the official abstract appears in the short.pdf file (which also appears in the research.pdf); a non-technical general description, or public abstract, appears in the public.pdf file. Title from title screen of research.pdf file (viewed on September 27, 2007) Vita. Includes bibliographical references.
APA, Harvard, Vancouver, ISO, and other styles
2

Stefani, Giovanni Laranjo de. "Sobre a técnica de Rod Drop em medidas de reatividade integral em bancos de controle e segurança de reatores." Universidade de São Paulo, 2013. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-04072013-145137/.

Full text
Abstract:
Este trabalho apresenta um estudo sobre o efeito de sombreamento em detectores de nêutrons, quando estes são utilizados em medidas de reatividade com a técnica de rod drop. O sombreamento pode ser entendido como uma mudança na eciência dos detectores, quando esta é dada em nêutrons detectados/ssão ocorrida no reator, sendo mais evidente nos detectores mais próximos ao banco sendo inserido. O método de análise, fundamentalmente teórica, baseou-se em simulações do reator IPEN/MB-01 utilizando o código CITATION e o programa MCNP. Em ambos os casos, os resultados são estáticos, mostrando os uxos neutrônicos apenas em duas situações: antes da inserção do banco, e após sua inserção. A reatividade, neste caso, é obtida utilizandose a expressão derivada da técnica de source jerk. Em adição ao estudo teórico, os dados de um experimento de rod drop realizado no reator IPEN/MB-01 também foram utilizados. Neste caso, a reatividade foi obtida com o método de cinética inversa, já que os dados experimentais são constituídos de valores que variam no tempo. Em todos os casos, fatores de correção para o efeito de sombreamento são propostos.
This work presents a study on the eect of shading in neutron detectors, when used in measures of reactivity with the rod drop technique. Shading can be understood as a change in the eciency of the detectors, when it is given in detected neutrons / ssion occurred in the reactor, more evident in the detectors closest to the bank being inserted. The method of analysis was based on simulations of reactor IPEN/MB-01, using the code CITATION and MCNP program. In both cases, the results were static, showing Neutronic ows in only two situations: before insertion of the control rod and after insertion. The measure of reactivity in this case was achieved using the expression derived from the source jerk technique. In addition to theoretical study, data from a rod drop experiment conducted in the reactor IPEN/MB-01 were also used. In this case, the reactivity was obtained using inverse kinetic method, since experimental data were set of values that vary with time. In all cases, correction factors for the shadowing eect have been proposed.
APA, Harvard, Vancouver, ISO, and other styles
3

長家, 康展. "確率論的手法による炉心解析に関する研究." 京都大学 (Kyoto University), 2012. http://hdl.handle.net/2433/165032.

Full text
APA, Harvard, Vancouver, ISO, and other styles
4

Pinto, Letícia Negrão. "Experimentos de efeitos de reatividade no reator nuclear- IPEN/MB-01." Universidade de São Paulo, 2012. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-23102012-145549/.

Full text
Abstract:
Pesquisas que tem como objetivo melhorar o desempenho de códigos de transporte de nêutrons e a qualidade de bases de dados de seções de choque nucleares são muito importantes para aumentar a acurácia de simulações e a qualidade de análises e predição de fenômenos no campo nuclear. Neste contexto, dados experimentais relevantes como medidas de reatividade induzida são necessários. O objetivo deste trabalho foi conduzir uma série de experimentos de medida de reatividade induzida, utilizando um reatímetro digital desenvolvido pelo IPEN. Os experimentos empregaram amostras metálicas inseridas na região central do núcleo do reator experimental IPEN/MB-01. A análise teórica foi realizada pelo código de física de reatores MCNP-5, desenvolvido e mantido pelo Los Alamos National Laboratory, e a biblioteca de dados nucleares ENDF/B-VII.0.
Researches that aim to improve the performance of neutron transport codes and quality of nuclear cross section databases are very important to increase the accuracy of simulations and the quality of the analysis and prediction of phenomena in the nuclear field. In this context, relevant experimental data such as reactivity worth measurements are needed. The objective of this work was to perform a series of experiments of reactivity worth measurements, using a digital reactivity meter developed at IPEN. The experiments employed metallic samples inserted in the central region of the core of the experimental IPEN/MB-01 reactor. The theoretical analysis was performed by the MCNP-5 reactor physics code, developed and maintained by Los Alamos National Laboratory, and the ENDF/B-VII.0 nuclear data library.
APA, Harvard, Vancouver, ISO, and other styles
5

PINTO, LETICIA N. "Experimentos de efeitos de reatividade no reator nuclear IPEN/MB-01." reponame:Repositório Institucional do IPEN, 2012. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10099.

Full text
Abstract:
Made available in DSpace on 2014-10-09T12:34:46Z (GMT). No. of bitstreams: 0
Made available in DSpace on 2014-10-09T14:01:16Z (GMT). No. of bitstreams: 0
Dissertação (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
APA, Harvard, Vancouver, ISO, and other styles

Book chapters on the topic "Reactivity Worth"

1

Yamanaka, Masao. "Sensitivity and Uncertainty of Criticality." In Accelerator-Driven System at Kyoto University Critical Assembly, 215–43. Singapore: Springer Singapore, 2021. http://dx.doi.org/10.1007/978-981-16-0344-0_8.

Full text
Abstract:
AbstractExcess reactivity and control rod worth are generally considered important reactor physics parameters for experimentally examining the neutron characteristics of criticality in a core, and for maintaining safe operation of the reactor core in terms of neutron multiplication in the core. For excess reactivity and control rod worth at KUCA, as well as at the Fast Critical Assembly in the Japan Atomic Energy Agency, special attention is given to analyzing the uncertainty induced by nuclear data libraries based on experimental data of criticality in representative cores (EE1 and E3 cores). Also, the effect of decreasing uncertainty on the accuracy of criticality is discussed in this study. At KUCA, experimental results are accumulated by measurements of excess reactivity and control rod worth. To evaluate the accuracy of experiments for benchmarks, the uncertainty originated from modeling of the core configuration should be discussed in addition to uncertainty induced by nuclear data, since the uncertainty from modeling has a potential to cover the eigenvalue bias more than uncertainty by nuclear data. Here, to investigate the uncertainty of criticality depending on the neutron spectrum of cores, it is very useful to analyze the reactivity of a large number of measurements in typical hard (EE1) and soft (E3) spectrum cores at KUCA.
APA, Harvard, Vancouver, ISO, and other styles
2

Pyeon, Cheol Ho. "Neutronics of Lead and Bismuth." In Accelerator-Driven System at Kyoto University Critical Assembly, 177–213. Singapore: Springer Singapore, 2021. http://dx.doi.org/10.1007/978-981-16-0344-0_7.

Full text
Abstract:
AbstractCross-section uncertainties of Pb and Bi isotopes could consequently affect the precision of nuclear design calculations of preliminary analyses, before the actual operation of upcoming ADS, since Pb and Bi are composed partly of coolant material (lead-bismuth eutectic: LBE) in ADS facilities. The main characteristics of LBE in ADS are recognized as follows: chemically inactive; high boiling point mechanically; excellent neutron economy caused by large scattering cross sections. From the viewpoint of neutronics, LBE exerts considerable impact on nuclear design parameters for numerical simulations of neutron interactions of Pb and Bi isotopes. As a suitable way of investigating cross-section uncertainties, sample reactivity worth measurements in critical states are considered effective with the use of reference and test materials in a zero-power state, such as a critical assembly, because integral parameter information on cross sections of test materials can be acquired experimentally. For the required experimental study on Pb and Bi nuclear data uncertainties, the sample reactivity worth experiments are carried out at the KUCA core by the substitution of reference (aluminum) for test (Pb or Bi) materials, and numerical simulations are performed with stochastic and deterministic calculation codes together with major nuclear data libraries.
APA, Harvard, Vancouver, ISO, and other styles

Conference papers on the topic "Reactivity Worth"

1

Manwaring, N. "Neck Shim Reactivity Worth in the Advanced Test Reactor." In Tranactions - 2019 Winter Meeting. AMNS, 2019. http://dx.doi.org/10.13182/t30794.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

Casoli, P., and N. Authier. "Reactivity worth measurements with CALIBAN and SILENE experimental reactors." In International Conference on Nuclear Data for Science and Technology. Les Ulis, France: EDP Sciences, 2007. http://dx.doi.org/10.1051/ndata:07271.

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

Pinto, Letícia Negrão, and Adimir dos Santos. "Reactivity worth measurements at the IPEN/MB-01 nuclear reactor." In XXXV BRAZILIAN WORKSHOP ON NUCLEAR PHYSICS. AIP, 2013. http://dx.doi.org/10.1063/1.4804110.

Full text
APA, Harvard, Vancouver, ISO, and other styles
4

Kikuchi, Shigeto, Kenji Tsuji, Akira Nishikawa, Hiromitsu Inagaki, Kenichi Yoshioka, Hisato Matsumiya, and Mitsuaki Yamaoka. "Experimental Study on Reactivity Worth of Burnable Poison in Ultra-Long Life, Small LMR." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22231.

Full text
Abstract:
Experimental study using an LWR-type critical assembly, NCA, has been conducted on the reactivity worth of the burnable poison (BP) that is employed in a small reactor, 4S, for achieving an extremely long core life. The experimental BP is composed of natural gadolinium oxide (Gd2O3) mixed in polyethylene. Three types of BPs are prepared: polyethylene without Gd, polyethylene with Gd/H ratio of 0.015at% and 0.943at%. Reactivity worth of each BP assembly is measured through change in critical water height. Power profile of fuel rods and flux profile are also measured. Analyses are conducted with a Monte-Carlo code, MCNP.
APA, Harvard, Vancouver, ISO, and other styles
5

Xiaobo, Wu, Peng Dan, Hong Jingyan, Lu Jin, and Hao Qian. "Physical Design on PMNSR With LEU Core." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-67580.

Full text
Abstract:
Prototype Miniature Neutron source Reactor (PMNSR) is a pool-tank type research reactor,applying high enrichment Uranium as fuel, light water as moderator and coolant, beryllium as reflector. Recently, in order to prevent nuclear proliferation, PMNSR carried out low enrichment uranium (LEU) core conversion, and the enrichment of U-235 decreased from 90% to under 20%. Research on PMNSR with LEU core mainly includes theory design, zero power experiment, core replacement. The physical design of PMNSR with LEU is the main part of theory design, which plays a great role in LEU conversion. At the first stage of LEU conversion, it performs preliminary physical calculation and analysis concerning U-235 fuel enrichment, and the number of critical fuel elements, the reactivity worth of control rod, the reactivity worth of top beryllium reflector, the neutron flux of inter-irradiation tube are calculated, which provides important data for the fuel elements design, fabrication, zero power test safety analysis and experiment for LEU conversion. In the second phase, it conducts the result verification on zero power test and preliminary physical design and a preliminary error analysis resulted from it thereof. More over, it modifies input file of LEU conversion, optimizes core element loading deployment, the reactivity worth of central control rod, the neutron flux rate of inner radiation site, offering statistics for the replacement and start-up experiments. In the last period, grounded on the counting abnormal analysis in loading, it explains the reasons with calculation results, completing PMNSR LEU conversion. PMNSR physical design takes the leading position in LEU conversion. It supplies reference data to ensure completion of PMNSR conversion and lays a theoretical foundation for Ghana and Nigeria MNSR LEU core conversion.
APA, Harvard, Vancouver, ISO, and other styles
6

Li, Xiaosheng, Linsen Li, Lianghui Peng, Xiaosong Chen, Zhaocan Meng, and Yaodong Chen. "Conceptual Core Design of HAPPY200 Reactor." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-82125.

Full text
Abstract:
The pressure and coolant temperature of Heating-reactor of Advanced low-Pressurized and Passive safetY system (HAPPY200) is significantly lower than PWR of the NPP, the core design and analysis were completed according to the design parameters and features of HAPPY200. The fuel assembly and its feature was firstly designed and studied based on the investigation of different types of fuel assemblies. Then the core configuration was studied and optimized according to the design parameters of HAPPY200; Eventually, neutronics calculation of the core was performed and key parameters were obtained including cycle length, power distribution, control rod worth, reactivity coefficients and etc. The study shows that with the core design HAPPY200 can be operated for 18 months in full power and reactivity control system can maintain criticality of the core in the full cycle. Due to the non-soluble boron design of the reactivity control scheme, moderator temperature coefficient and isothermal temperature coefficient are both negative, the Doppler temperature coefficients and power coefficients in different phase of the lifetime and in different power levels are also negative, therefore, the reactivity safety of the reactor core can be ensured.
APA, Harvard, Vancouver, ISO, and other styles
7

Blaise, Patrick, Frederic Mellier, and Philippe Fougeras. "Application of the Modified Source Multiplication (MSM) technique to subcritical reactivity worth measurements in thermal and fast reactor systems." In 2009 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA). IEEE, 2009. http://dx.doi.org/10.1109/animma.2009.5503677.

Full text
APA, Harvard, Vancouver, ISO, and other styles
8

Ohgama, Kazuya, Gerardo Aliberti, Nicolas E. Stauff, Shigeo Ohki, and Taek K. Kim. "Comparative Study on Neutronics Characteristics of a 1500 MWe Metal Fuel Sodium-Cooled Fast Reactor." In 2016 24th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2016. http://dx.doi.org/10.1115/icone24-60455.

Full text
Abstract:
Under the cooperative effort of the Civil Nuclear Energy R&D Working Group within the framework of the U.S.-Japan bilateral, Argonne National Laboratory (ANL) and Japan Atomic Energy Agency (JAEA) have been performing benchmark study using Japan Sodium-cooled Fast Reactor (JSFR) design with metal fuel. In this benchmark study, core characteristic parameters at the beginning of cycle were evaluated by the best estimate deterministic and stochastic methodologies of ANL and JAEA. The results obtained by both institutions are agreed well with less than 200 pcm of discrepancy on the neutron multiplication factor, and less than 3% of discrepancy on the sodium void reactivity, Doppler reactivity, and control rod worth. The results by the stochastic and deterministic were compared in each party to investigate impacts of the deterministic approximation and to understand potential variations in the results due to different calculation methodologies employed. Impacts of the nuclear data libraries were also investigated using a sensitivity analysis methodology.
APA, Harvard, Vancouver, ISO, and other styles
9

Lindley, Benjamin A., N. Zara Zainuddin, Fausto Franceschini, and Geoffrey T. Parks. "Analysis of Advanced PWR Loading Schemes for Transuranic Incineration in Thorium." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-15328.

Full text
Abstract:
It is difficult to perform multiple recycle of transuranic (TRU) isotopes in PWRs as the moderator temperature coefficient (MTC) tends to become positive after a few recycles and the core may have positive reactivity when fully voided. Due to the favorable impact on the MTC and void coefficient fostered by use of thorium (Th), the possibility of performing Th-TRU multiple-recycle in reduced-moderation PWRs (RMPWRs) is under consideration. The simplest way to reduce the moderation in a PWR is to increase the fuel pin diameter. This configuration improves the trade-off between achievable burn-up and MTC, but is ultimately limited by thermal-hydraulic constraints. Heterogeneous recycle with the bred uranium (U3) and the TRU are arranged in separate pins was found to be neutronically preferable to a homogeneous configuration. Spatial separation also enables the U3 and TRU to be refueled on different batch schemes. These techniques allow satisfactory discharge burn-up while ensuring negative MTC and fully voided reactivity, with the pin diameter of a standard PWR increased from 9.5 mm to 11 mm. Reactivity control is a key challenge due to the reduced worth of neutron absorbers and their detrimental effect on the void coefficients, especially when diluted, as is the case for soluble boron. It seems necessary to control the core using control rods to keep the fully voided reactivity negative. A preliminary analysis indicates that this is feasible.
APA, Harvard, Vancouver, ISO, and other styles
10

Awan, Muhammad Qasim, Liangzhi Cao, and Hongchun Wu. "Burnable Poisons Alternative Configurations in AT-FCM PWR Fuel Assembly." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-66444.

Full text
Abstract:
The Fukushima Daiichi Nuclear Power Plant accident in Japan was one of the severest accidents in history of nuclear power plants. This accident changed the prospect of the Nuclear Engineers all around the globe, regarding safety enhancement of nuclear reactors. Since then many aspects of nuclear reactors regarding the improvements of safety features are under investigation and R&D efforts are underway around the world. Use of innovative fuels in present as well as future reactor designs is one of the major potential areas of these ongoing efforts. Fully Ceramic Micro-Encapsulated (FCM) fuel originally developed for use in high temperature gas cooled nuclear reactors, has proven worth for operating in high temperature environment with high burn-up. Due to its additional fission product barrier in the form of strong SiC layer, it is worth using for application as PWR fuel, thus providing potential benefits related to safety and operational aspects of power plant. However, use of FCM fuel in a PWR also has some operational constraints such as the moderator temperature coefficient (MTC) of reactivity has less negative value and even becomes positive when higher concentration of soluble boron is used for the reactivity control. Thus, use of burnable poison material becomes more important to control the access reactivity throughout the cycle length in such a way the quantity of soluble boron to be used is much lower to prevent the positive MTC value or even soluble boron free operation is possible. In present studies a new candidate designs of PWR fuel assembly of 12×12 square array configuration has been used to study the BP material impact on cycle length. Monte Carlo code MVP-BURN is utilized for the analysis to accurately model the double heterogeneity arising due to TRISO type fuel. Two standard materials i.e. Erbia and Gadolinia are used and different configuration including mixing of BP in matrix material, fuel kernel and in QUADRISO form are analyzed and compared with each other. Impact of the residual poison are also analyzed and additional enrichment required to overcome the impact of residual BP material reactivity are calculated. Different configurations support different BP materials. However, it has been found that with an appropriate combination of both materials and configuration, it is possible to minimize the use of soluble boron. Finally, the recommended assembly configuration is analyzed for MTC value during the entire cycle length, showing sustainability of negative values of MTC for the region of interest. With this kind of arrangements, it is possible to use FCM type fuel for present as well as future generations of the PWRs.
APA, Harvard, Vancouver, ISO, and other styles

Reports on the topic "Reactivity Worth"

1

Lell, Richard. ZPPR-15 Small Reactivity Worth Experiments. Office of Scientific and Technical Information (OSTI), April 2020. http://dx.doi.org/10.2172/1786971.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

Klann, R. T., and G. Perret. Reactivity-worth estimates of the OSMOSE samples in the MINERVE reactor R1-UO2 configuration. Office of Scientific and Technical Information (OSTI), October 2007. http://dx.doi.org/10.2172/917241.

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

Zhong, Z., R. T. Klann, and Nuclear Engineering Division. Reactivity-worth estimates of the OSMOSE samples in the MINERVE reactor R1-MOX, R2-UO2 and MORGANE/R configurations. Office of Scientific and Technical Information (OSTI), August 2007. http://dx.doi.org/10.2172/915031.

Full text
APA, Harvard, Vancouver, ISO, and other styles
You might also be interested in the extended bibliographies on the topic 'Reactivity Worth' for particular source types:
Journal articles
We offer discounts on all premium plans for authors whose works are included in thematic literature selections. Contact us to get a unique promo code!

To the bibliography