Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika最新文献_第8页

Nuclear Energy System Modelling Application Package: Functional Overview and Examples 核能系统建模应用程序包:功能概述和示例

Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika Pub Date : 2022-06-01 DOI: 10.26583/npe.2022.2.14

A. Andrianov, I. Kuptsov, T. Osipova, Anastasia Alekseevna Spiridonova, O. Andrianova, Tat’yana Vladimirovna Utianskaia

{"title":"Nuclear Energy System Modelling Application Package: Functional Overview and Examples","authors":"A. Andrianov, I. Kuptsov, T. Osipova, Anastasia Alekseevna Spiridonova, O. Andrianova, Tat’yana Vladimirovna Utianskaia","doi":"10.26583/npe.2022.2.14","DOIUrl":"https://doi.org/10.26583/npe.2022.2.14","url":null,"abstract":"The paper provides a brief description of the functionality of the nuclear energy system modelling application package (NESAPP), including a list of modelling objects, key assumptions and areas of application. NESAPP consists of the following main modules: NUDAPS (a module for calculating thermal neutron cross-sections, resonance integrals and one-group neutron cross-sections, and associated uncertainties), NUCLEX (a module for calculating the evolution of the nuclide composition and characteristics of nuclear fuel in reactors and at the nuclear fuel cycle front-end and back-end steps), NUCAB (a module for adjusting isotopic composition and blending), FANES (a module for analysing material flows and integrating data in nuclear energy evolution scenarios), ECNES (a module for assessing economic performance metrics for the nuclear energy evolution scenarios). Each of the modules is a calculation tool that can be used as independent or integrated into the software for technical and economic modelling of nuclear energy systems. Various calculation models are implemented in the modules, allowing users to evaluate the methodological component of the calculation uncertainty in scenario modelling studies and the functionality for assessing the impact of initial data uncertainties on the resulting indicators. The authors also provide some examples of applying NESAPP.","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2022-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74141512","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

On the Concept of «Effective Delayed Neutron Fraction» 关于“有效延迟中子分数”的概念

Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika Pub Date : 2022-06-01 DOI: 10.26583/npe.2022.2.16

A. G. Yuferov

{"title":"On the Concept of «Effective Delayed Neutron Fraction»","authors":"A. G. Yuferov","doi":"10.26583/npe.2022.2.16","DOIUrl":"https://doi.org/10.26583/npe.2022.2.16","url":null,"abstract":"The article considers methodological issues related to the conceptual and terminological apparatus of the dynamics of nuclear reactors. Based on an elementary analysis of the standard point reactor kinetics equations, the author shows that it is necessary to clarify the physical meaning of the parameter β included in the equations, which is traditionally interpreted as the “effective delayed neutrons fraction” (EDNF). It follows directly from the kinetics equations that the parameter β, which appears in these equations as the EDNF, is, from the point of view of the neutron balance, the fraction of prompt neutrons consumed for the generation of delayed neutron precursors (DNPs), and, from the point of view of the DNP balance, the DNP yield per prompt neutron in a single fission event. With these interpretations taken into account, the role of the β parameter is considered in situations related with its adjustment by multiplying it by the “delayed neutron efficiency factor” and with the establishment of the actual fractions of prompt and delayed neutrons. In particular, it is shown that:\u0000 the statement “if the delayed neutron fraction is β, then the prompt neutron fraction is equal to 1 – β”, used in the problems of analyzing the nuclear reactor dynamics as a starting position, cannot be considered applicable to any reactor conditions;\u0000 an increase in the β parameter by multiplying it by the “delayed neutron efficiency factor” leads, contrary to traditional interpretations, not to an increase but to a decrease in neutron reproduction in a supercritical reactor.\u0000 The proposed clarifications are appropriate both in terms of more adequate descriptions of processes in nuclear reactors and in relation to the formulations of nuclear safety requirements.","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2022-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81745929","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Calculation of Enriched Uranium Products Costs in Multi&Threaded Cascades of Enrichment Process 多线程级联浓缩过程中浓缩铀产品成本的计算

Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika Pub Date : 2022-06-01 DOI: 10.26583/npe.2022.2.11

E. V. Semyonov, V. V. Kharitonov

引用次数: 0

Innovative Methods of Management of Radioactively Contaminated NPP Water – a Windows of Opportunities 核电站放射性污染水管理的创新方法-机遇之窗

Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika Pub Date : 2022-06-01 DOI: 10.26583/npe.2022.2.10

A. S. Chugunov, Vadim Aleksandrovich Vinnitskij

引用次数: 0

Thermophysical Studies of Alkaline Liquid Metal Coolants. Izvestiya vuzov 碱性液态金属冷却剂的热物理研究。Izvestiya vuzov

Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika Pub Date : 2022-06-01 DOI: 10.26583/npe.2022.2.05

J. Kuzina, A. Sorokin, N. A. Denisova

引用次数: 0

Comprehensive Analysis of Proliferation Protection of Uranium due to the Presence of 232U and its Decay Products 232U及其衰变产物对铀防扩散的综合分析

Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika Pub Date : 2022-06-01 DOI: 10.26583/npe.2022.2.15

G. Kulikov, A. Shmelev, V. Apse, E. Kulikov

引用次数: 0

Experience of the Use of Detection Systems for Loose Parts and Weakly Fixed Objects in the Coolant Circulation Circuit of Novovoronezh NPP Reactor Installations 新沃罗涅日核电站装置冷却剂循环回路中松散部件和弱固定物体检测系统的使用经验

Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika Pub Date : 2022-06-01 DOI: 10.26583/npe.2022.2.02

A. Voronov, M. T. Slepov

引用次数: 1

Carrying out Calculations of Radiation Safety During Unloading and Disassembly of Cores of Spent Removable Parts of Reactors with Liquid Metal Coolant of Submarines 潜艇液态金属冷却剂反应堆废可拆卸件堆芯卸拆过程辐射安全计算

Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika Pub Date : 2022-06-01 DOI: 10.26583/npe.2022.2.07

Elena Vladimirovnа Devkina, I. Suslov, V. Chernov

{"title":"Carrying out Calculations of Radiation Safety During Unloading and Disassembly of Cores of Spent Removable Parts of Reactors with Liquid Metal Coolant of Submarines","authors":"Elena Vladimirovnа Devkina, I. Suslov, V. Chernov","doi":"10.26583/npe.2022.2.07","DOIUrl":"https://doi.org/10.26583/npe.2022.2.07","url":null,"abstract":"The results of calculations conducted to substantiate radiation safety while handling spent removable sections (SRS) of reactors with a liquid metal coolant (LMC) for nuclear submarines (NS) are presented in the article. The spent removable sections of reactors with liquid metal coolant for nuclear submarines are the sources of intense neutron and gamma radiation. Shielding should ensure the dose rate level for neutrons and gamma radiation which is not exceeding the values allowed for transportation of nuclear materials established by the NP-053-04 therefore it will attenuate emission of neutrons and gamma quanta by several orders of magnitude.\u0000 A homogeneous model of the reactor core was used for calculations. Sources of neutrons and photons in the spent nuclear fuel (SNF) of the SRS, sources of photons in the reactor control devices and in construction materials (the reactor vessel and grids of fuel rods) have been taken into consideration while conducting the calculations. The computer code MCNP-4B was employed to calculate dose rates for neutrons and photons.\u0000 In most cases direct calculations of dose rates for neutrons and secondary gamma-quanta using the MCNP-4B code provided acceptable results with admissible methodical errors. For the tasks with sources of gamma quanta direct calculation using the MCNP-4B brought unsatisfactory results due to strong attenuation.\u0000 Various methods were applied to reduce dispersion: the first one is to assign importance to the cells and the second one is the method of weight windows iteration.\u0000 Values of dose rates were obtained with acceptable errors. The results of the calculations provided necessary information to conduct operations to unload spent nuclear fuel from the SRS. The results of performed calculations were also used in the design and manufacturing of the shielding.","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2022-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"76512772","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Computational and Experimental Justification of Increasing the Efficiency of the Regenerative Heat Exchanger of the Steam Generator Purge System of the NPP-2006 Project (RU V-392M) 提高NPP-2006项目(RU V-392M)蒸汽发生器吹扫系统蓄热式换热器效率的计算与实验论证

Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika Pub Date : 2022-06-01 DOI: 10.26583/npe.2022.2.03

S. V. Yaurov, A. V. Borovoy, A. Yudin, M. Bolgov, A. Danilov

引用次数: 0

Simulating Sodium Purification from Oxygen by a Soluble Getter. Izvestiya vuzov 用可溶性吸气剂模拟从氧中提纯钠。Izvestiya vuzov

Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika Pub Date : 2022-06-01 DOI: 10.26583/npe.2022.2.08

Ruslana Оlegovna Sutyagina, V. V. Alekseev, Ivan Аlekseevich Sutyagin

引用次数: 0