Christopher Ashe , P.N. Maya , Stuart I. Muldrew , Shishir Deshpande
{"title":"球形托卡马克电站过程设计与SARAS的标杆设计","authors":"Christopher Ashe , P.N. Maya , Stuart I. Muldrew , Shishir Deshpande","doi":"10.1016/j.fusengdes.2025.115359","DOIUrl":null,"url":null,"abstract":"<div><div>Uncertainty in systems codes can be analyzed based on the assumptions in the models used, and their combinations of input parameters before optimization. In this paper we compare the PROCESS and SARAS codes across a range of spherical tokamak designs that have been identified as possible pilot plant and commercial designs on the Indian-DEMO programme. Overall both codes produce partially similar results though differences in the calculation and treatment of the edge safety factor lead to discrepancies in the calculation of other key parameters with differences of <span><math><mrow><mo>≈</mo><mo>±</mo><mspace></mspace><mn>20</mn><mtext>%</mtext></mrow></math></span>. Mainly with plasma current, <span><math><mi>β</mi></math></span> components and subsequently confinement time calculations. Bootstrap current fraction calculations were shown to be unreliable and out of the regime of future power plants, highlighting the need for new surrogate models closer to power plant conditions . Using Monte Carlo based uncertainty quantification focusing on the epistemic uncertainty of the inboard toroidal field coil leg we see reasonable agreement in stress quantification between the two codes. The pessimistic uncertainty assumption still shows room for performance recovery in a reduced toroidal field strength scenario.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115359"},"PeriodicalIF":2.0000,"publicationDate":"2025-08-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Benchmarking of spherical tokamak power plant design in PROCESS and SARAS\",\"authors\":\"Christopher Ashe , P.N. Maya , Stuart I. Muldrew , Shishir Deshpande\",\"doi\":\"10.1016/j.fusengdes.2025.115359\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Uncertainty in systems codes can be analyzed based on the assumptions in the models used, and their combinations of input parameters before optimization. In this paper we compare the PROCESS and SARAS codes across a range of spherical tokamak designs that have been identified as possible pilot plant and commercial designs on the Indian-DEMO programme. Overall both codes produce partially similar results though differences in the calculation and treatment of the edge safety factor lead to discrepancies in the calculation of other key parameters with differences of <span><math><mrow><mo>≈</mo><mo>±</mo><mspace></mspace><mn>20</mn><mtext>%</mtext></mrow></math></span>. Mainly with plasma current, <span><math><mi>β</mi></math></span> components and subsequently confinement time calculations. Bootstrap current fraction calculations were shown to be unreliable and out of the regime of future power plants, highlighting the need for new surrogate models closer to power plant conditions . Using Monte Carlo based uncertainty quantification focusing on the epistemic uncertainty of the inboard toroidal field coil leg we see reasonable agreement in stress quantification between the two codes. The pessimistic uncertainty assumption still shows room for performance recovery in a reduced toroidal field strength scenario.</div></div>\",\"PeriodicalId\":55133,\"journal\":{\"name\":\"Fusion Engineering and Design\",\"volume\":\"221 \",\"pages\":\"Article 115359\"},\"PeriodicalIF\":2.0000,\"publicationDate\":\"2025-08-28\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Fusion Engineering and Design\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0920379625005551\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379625005551","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
Benchmarking of spherical tokamak power plant design in PROCESS and SARAS
Uncertainty in systems codes can be analyzed based on the assumptions in the models used, and their combinations of input parameters before optimization. In this paper we compare the PROCESS and SARAS codes across a range of spherical tokamak designs that have been identified as possible pilot plant and commercial designs on the Indian-DEMO programme. Overall both codes produce partially similar results though differences in the calculation and treatment of the edge safety factor lead to discrepancies in the calculation of other key parameters with differences of . Mainly with plasma current, components and subsequently confinement time calculations. Bootstrap current fraction calculations were shown to be unreliable and out of the regime of future power plants, highlighting the need for new surrogate models closer to power plant conditions . Using Monte Carlo based uncertainty quantification focusing on the epistemic uncertainty of the inboard toroidal field coil leg we see reasonable agreement in stress quantification between the two codes. The pessimistic uncertainty assumption still shows room for performance recovery in a reduced toroidal field strength scenario.
期刊介绍:
The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.