Annals of Nuclear Energy最新文献_第9页

Cross-Verification and validation of steady-state OPAL research reactor neutronic models using OpenMC and MCNP5 Codes: A foundation for advanced coupled simulations

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-07 DOI: 10.1016/j.anucene.2025.111324

Djahid Lababsa , Hakim Mazrou , Djalal Hamed , Abdelkader Aouaichia , Hamza Hasnaoui

{"title":"Cross-Verification and validation of steady-state OPAL research reactor neutronic models using OpenMC and MCNP5 Codes: A foundation for advanced coupled simulations","authors":"Djahid Lababsa , Hakim Mazrou , Djalal Hamed , Abdelkader Aouaichia , Hamza Hasnaoui","doi":"10.1016/j.anucene.2025.111324","DOIUrl":"10.1016/j.anucene.2025.111324","url":null,"abstract":"<div><div>This study develops, verifies, and validates high-fidelity steady-state neutronic models of the OPAL research reactor using OpenMC and MCNP5. The models were developed based on a consistent methodology, utilizing identical input data, geometric modeling, and cross-section libraries, minimizing discrepancies from external factors, ensuring a solid foundation for subsequent code-to-code comparisons.</div><div>Verification and validation were conducted through comparisons with results from SERPENT and MCNP6, as well as experimental data. Our results showed strong agreement with the experimental data, including control rod worth calculations within 3% and axial peak factor differences averaging 2% for MCNP5 and 3% for OpenMC. Differences in isothermal temperature and void coefficients were approximately 1 pcm/°C and 7 pcm/%, respectively. Deviations from SERPENT and MCNP6 for few key parameters were within acceptable limits, consistent with reference studies, and attributed to variations in modeling, code differences, and Monte Carlo statistical uncertainties.</div><div>Finally, a comprehensive code-to-code comparison of key neutronic parameters, such as reactivity, flux distributions, kinetic parameters, and power distribution, showed excellent agreement between OpenMC and MCNP5, with relative differences under 1% for most parameters.</div><div>Overall, this study confirms the reliability of the developed models for simulating the OPAL reactor and establishes OpenMC as a viable alternative to MCNP for reactor physics simulations, laying the foundation for future coupling with thermal–hydraulic models.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"217 ","pages":"Article 111324"},"PeriodicalIF":1.9,"publicationDate":"2025-03-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143563277","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Improving neutron economy of a Lead-Bismuth Eutectic-Cooled reactor using Modified-CANDLE axial fuel shuffling

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-06 DOI: 10.1016/j.anucene.2025.111328

Nina Widiawati , R.Andika Putra Dwijayanto , Fitria Miftasani , Nuri Trianti , Anni Nuril Hidayati , Maryam Afifah , Ratna Dewi Syarifah , Zaki Su'ud

{"title":"Improving neutron economy of a Lead-Bismuth Eutectic-Cooled reactor using Modified-CANDLE axial fuel shuffling","authors":"Nina Widiawati , R.Andika Putra Dwijayanto , Fitria Miftasani , Nuri Trianti , Anni Nuril Hidayati , Maryam Afifah , Ratna Dewi Syarifah , Zaki Su'ud","doi":"10.1016/j.anucene.2025.111328","DOIUrl":"10.1016/j.anucene.2025.111328","url":null,"abstract":"<div><div>LWRs do not effectively utilize natural uranium as fuel, harnessing less than 1% of its energy potential. Furthermore, initial studies show that conventional fast reactors require higher uranium enrichment and fuel reprocessing, which are expensive technology. The Modified-CANDLE strategy enables the direct use of natural uranium without enrichment or reprocessing. This study implements modified-CANDLE axial fuel shuffling in a lead–bismuth eutectic (LBE)-cooled fast reactor to examine its impact on reactor performance compared to radial fuel shuffling. The calculations use the SRAC code and the JENDL 4.0 nuclear data library. This research evaluates the effective multiplication factor (k-eff), power density, power peaking factor (PPF), and neutron leakage over a 15-year fuel cycle. The research indicates that axial fuel shuffling is more efficient at sustaining the reactor’s reactivity than radial shuffling. Therefore, axial fuel shuffling can improve neutron economy compared to radial fuel shuffling.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"217 ","pages":"Article 111328"},"PeriodicalIF":1.9,"publicationDate":"2025-03-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143550075","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

A review of the scientific contributions by Barry Ganapol

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-06 DOI: 10.1016/j.anucene.2025.111253

P. Ravetto , P. Saracco

引用次数: 0

Integrated thermal power measurement in the modified STACY for the performance inspections

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-06 DOI: 10.1016/j.anucene.2025.111323

Shouhei Araki , Eiju Aizawa , Takahiko Murakami , Yu Arakaki , Yuta Tada , Yutaka Kamikawa , Kenta Hasegawa , Tomoki Yoshikawa , Masato Sumiya , Masakazu Seki , Junichi Ishii , Kazuhiko Izawa , Daiki Iwahashi , Shigeki Shiba , Satoshi Gunji

{"title":"Integrated thermal power measurement in the modified STACY for the performance inspections","authors":"Shouhei Araki , Eiju Aizawa , Takahiko Murakami , Yu Arakaki , Yuta Tada , Yutaka Kamikawa , Kenta Hasegawa , Tomoki Yoshikawa , Masato Sumiya , Masakazu Seki , Junichi Ishii , Kazuhiko Izawa , Daiki Iwahashi , Shigeki Shiba , Satoshi Gunji","doi":"10.1016/j.anucene.2025.111323","DOIUrl":"10.1016/j.anucene.2025.111323","url":null,"abstract":"<div><div>Japan Atomic Energy Agency (JAEA) has modified the Static Experimental Critical Facility (STACY) to a heterogeneous system using fuel rods in order to obtain criticality characteristics of fuel debris. Thermal power measurement was required for the calibration of a power meter system in the modified STACY in order to conduct a series of performance inspections and operation. We measured the thermal power using the modified activation method that combined MVP and PHITS code because neutron flux distribution cannot be measured experimentally. Four operations were conducted for the thermal power measurement. The power meter was calibrated by using three operational data and tested with one operational data. It was found that the calibration of the power meter system was successfully agreed within 3% with the results measured by the activation method.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"217 ","pages":"Article 111323"},"PeriodicalIF":1.9,"publicationDate":"2025-03-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143550076","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Sensitivity analysis of parameters and optimization of produced entropy in a nuclear reactor with equilateral fuel rod arrangement and variable angle turbulators

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-05 DOI: 10.1016/j.anucene.2025.111310

Abdullah A.A.A. Al-Rashed, Abdulwahab A. Alnaqi, Jalal Alsarraf

{"title":"Sensitivity analysis of parameters and optimization of produced entropy in a nuclear reactor with equilateral fuel rod arrangement and variable angle turbulators","authors":"Abdullah A.A.A. Al-Rashed, Abdulwahab A. Alnaqi, Jalal Alsarraf","doi":"10.1016/j.anucene.2025.111310","DOIUrl":"10.1016/j.anucene.2025.111310","url":null,"abstract":"<div><div>This paper investigates the produced entropy (ENT), including thermal ENT, fluid loss, total ENT, and the Bejan number (Be) in a nuclear reactor with equilateral fuel rod arrangements. The fuel rods are placed within tubes that have diameters varying from 3.1 to 10.1 cm. The rods are vertically positioned in the reactor at a fixed distance, and nanofluids are used to cool them. Turbulator (TUR) blades with angles varying from 0 to 6 degrees and heights from 0 to 13 cm are employed in the nanofluid flow. To enhance the analysis, machine learning methods are used for sensitivity analysis of parameters and optimization of outputs. The results of this study indicate that increasing the tube diameter and the height of the TUR blades leads to an increase in fluid loss ENT, while changes in blade angle have a minimal effect on fluid loss ENT. Increasing the tube diameter and blade length significantly increases thermal ENT and total ENT. Blade angle also has an effect, with thermal ENT decreasing as the angle increases. Changes in blade height, angle, and tube diameter containing the fluid flow result in a 1.8 % variation in the Be. The results demonstrate that tube diameter, blade length, and TUR blade angle are all important parameters in determining the Be in the reactor. An increase in tube diameter significantly raises the Be, while an increase in blade length decreases it. The angle of the blades also affects the Be, with an increase in angle leading to a decrease in the Be.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"217 ","pages":"Article 111310"},"PeriodicalIF":1.9,"publicationDate":"2025-03-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143550073","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Experimental study on flux allocation characteristics of annular fuel bundle channel

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-04 DOI: 10.1016/j.anucene.2025.111316

Jinyang Li , Shouxu Qiao , Sijia Hao , Yu Zou , Xupeng Li , Sichao Tan , Ruifeng Tian

引用次数: 0

Correcting nuclide concentration fields and optimizing monitoring locations based on environmental-monitoring data

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-04 DOI: 10.1016/j.anucene.2025.111326

Yue Qi , Yang Jie , Chen Jiachen , Meng Binchi , Shi Yikun , Wu Feifei , Lian Bing , Wang Yan

{"title":"Correcting nuclide concentration fields and optimizing monitoring locations based on environmental-monitoring data","authors":"Yue Qi , Yang Jie , Chen Jiachen , Meng Binchi , Shi Yikun , Wu Feifei , Lian Bing , Wang Yan","doi":"10.1016/j.anucene.2025.111326","DOIUrl":"10.1016/j.anucene.2025.111326","url":null,"abstract":"<div><div>Radioactive materials can be released into the external environment after nuclear facility accidents. Therefore, it is necessary to rapidly assess the spatial distribution of radioactive nuclides. Using only the concentration distribution of radioactive nuclides predicted by the atmospheric dispersion models may result in deviations from the actual concentration distribution. To make the predicted distribution more consistent with the actual distribution, a method based on Kriging interpolation was developed to rapidly correct the predicted concentration distribution using a small amount of environmental aerosol monitoring data. In addition, a method for optimizing environmental aerosol monitoring locations based on a differential evolution algorithm was developed to guide the placement of more representative monitoring locations and improve the accuracy of the corrected concentration distribution. The results indicated that using optimized monitoring locations to obtain environmental monitoring data enhanced the accuracy of prediction in key areas in the constructed case-studies, reducing false-negative areas by 97%.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"216 ","pages":"Article 111326"},"PeriodicalIF":1.9,"publicationDate":"2025-03-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143534351","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Prediction of composite neutron source spectra by combination of JENDL-5 and PHITS

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-04 DOI: 10.1016/j.anucene.2025.111256

Tatsuhiko Ogawa

引用次数: 0

Numerical study on flow instability development of natural circulation in narrow channel under medium-to-high pressure

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-04 DOI: 10.1016/j.anucene.2025.111322

Yao Yao , Tao Zhou , Jianyu Tang , Dongli Huang , Zefeng Wang

{"title":"Numerical study on flow instability development of natural circulation in narrow channel under medium-to-high pressure","authors":"Yao Yao , Tao Zhou , Jianyu Tang , Dongli Huang , Zefeng Wang","doi":"10.1016/j.anucene.2025.111322","DOIUrl":"10.1016/j.anucene.2025.111322","url":null,"abstract":"<div><div>Natural circulation flow instability is an important phenomenon for nuclear system safety, especially in narrow channels which have a broad application prospect. However, the small gap of narrow channels can easily lead to the narrow-space effect, resulting in mechanisms and performance of instability different from those in conventional channels. Medium-to-high pressure is a common condition in nuclear systems. Therefore, it is necessary to study flow instability in narrow channels under medium-to-high pressure. The ultimate goal is to effectively avoid the instability and improve the safety of nuclear systems. This manuscript investigates the characteristics of natural circulation instability in a narrow channel with deionized water under medium-to-high pressure (7.0 MPa-15.0 MPa). Results provide new insights into the safety and reliability of nuclear reactor cooling systems, supporting the establishment of more accurate and reliable natural circulation systems. A numerical study establishes a model of natural circulation loop including a narrow channel via system code RELAP5 based on a well-validated natural circulation test facility. The instability development is divided into three stages, natural circulation stable flow, instability flow (no reverse flow), and instability flow (reverse flow) or periodic dryout instability, according to the amplitudes and periods of mass flow rate. The proposed RELAP5 model demonstrates the relationship between mass flow rate and pressure drop on a time scale of a few seconds in every stage. Mass flow rate, exit quality, two-phase length, and flow regime are examined throughout all stages. Results indicate that increasing system pressure and inlet subcooling have a significant inhibitory effect on instability oscillation.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"216 ","pages":"Article 111322"},"PeriodicalIF":1.9,"publicationDate":"2025-03-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143534219","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Research on steady-state behavior of natural circulation with internally heated fluids of liquid-fueled molten salt reactor

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-04 DOI: 10.1016/j.anucene.2025.111320

Ying Cao , Weishi Wan , Chong Zhou

引用次数: 0