Prospects for Development of an Innovative Water-Cooled Nuclear Reactor for Supercritical Parameters of Coolant

S. G. Kalyakin; P. L. Kirillov; Yu. D. Baranaev; A. P. Glebov; G. P. Bogoslovskaya; M. P. Nikitenko; V. M. Makhin; A. N. Churkin

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Prospects for Development of an Innovative Water-Cooled Nuclear Reactor for Supercritical Parameters of Coolant

机译：开发冷却剂超临界参数的新型水冷核反应堆的前景

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The state of nuclear power engineering as of February 1, 2014 and the accomplished elaborations of a supercritical-pressure water-cooled reactor are briefly reviewed, and the prospects of this new project are discussed based on this review. The new project rests on the experience gained from the development and operation of stationary water-cooled reactor plants, including VVERs, PWRs, BWRs, and RBMKs (their combined service life totals more than 15 000 reactor-years), and long-term experience gained around the world with operation of thermal power plants the turbines of which are driven by steam with supercritical and ultrasupercritical parameters. The advantages of such reactor are pointed out together with the scientific-technical problems that need to be solved during further development of such installations. The knowledge gained for the last decade makes it possible to refine the concept and to commence the work on designing an experimental small-capacity reactor.

机译：简要回顾了截至2014年2月1日的核电工程状况以及超临界压力水冷堆的已完成工程，并在此基础上讨论了该新项目的前景。新项目基于从固定式水冷反应堆工厂的开发和运营中获得的经验，包括VVER，PWR，BWR和RBMK（它们的总使用寿命超过15,000个反应堆年），以及长期经验火力发电厂在全球范围内获得了成功，其涡轮机由具有超临界和超超临界参数的蒸汽驱动。指出了这种反应器的优点以及在进一步发展这种装置过程中需要解决的科学技术问题。过去十年中获得的知识使得有可能对概念进行完善，并开始进行实验性小容量反应堆的设计工作。

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《Thermal engineering》 |2014年第8期|551-557|共7页
作者
S. G. Kalyakin; P. L. Kirillov; Yu. D. Baranaev; A. P. Glebov; G. P. Bogoslovskaya; M. P. Nikitenko; V. M. Makhin; A. N. Churkin;
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作者单位

State Scientific Center of the Russian Federation-Institute for Physics and Power Engineering named after A. I. Leypunsky, pl. Bondarenko 1, Obninsk, Kaluga oblast, 249033 Russia;

State Scientific Center of the Russian Federation-Institute for Physics and Power Engineering named after A. I. Leypunsky, pl. Bondarenko 1, Obninsk, Kaluga oblast, 249033 Russia;

State Scientific Center of the Russian Federation-Institute for Physics and Power Engineering named after A. I. Leypunsky, pl. Bondarenko 1, Obninsk, Kaluga oblast, 249033 Russia;

State Scientific Center of the Russian Federation-Institute for Physics and Power Engineering named after A. I. Leypunsky, pl. Bondarenko 1, Obninsk, Kaluga oblast, 249033 Russia;

State Scientific Center of the Russian Federation-Institute for Physics and Power Engineering named after A. I. Leypunsky, pl. Bondarenko 1, Obninsk, Kaluga oblast, 249033 Russia;

OKB Gidropress, ul. Ordzhonikidze 21, Podolsk, Moscow oblast, 142103 Russia;

OKB Gidropress, ul. Ordzhonikidze 21, Podolsk, Moscow oblast, 142103 Russia;

OKB Gidropress, ul. Ordzhonikidze 21, Podolsk, Moscow oblast, 142103 Russia;

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原文格式 PDF
正文语种 eng
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关键词
reactor; nuclear power installation; supercritical water pressure; 4th generation; advantages of the INPRO methodology;

机译：反应堆;核电装置;超临界水压第四代;INPRO方法的优势;

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1. The Use of Supercritical Parameters of a Coolant—a Promising Path to Development of Nuclear Power Plant Water-Cooled Reactors in the 21st Century [J] . B. A. Gabaraev, V. N. Smolin, S. L. Solovev Thermal engineering . 2006,第9期

机译：使用冷却剂的超临界参数-21世纪开发核电站水冷堆的有希望的途径
2. Prospects for and problems of using light-water supercritical-pressure coolant in nuclear reactors in order to increase the efficiency of the nuclear fuel cycle [J] . Alekseev P.N., Semchenkov Y.M., Sedov A.A., Physics of atomic nuclei . 2011,第13期

机译：在核反应堆中使用轻水超临界冷却剂以提高核燃料循环效率的前景和问题
3. Changing over to supercritical parameters: the way to advance nuclear power stations with water-cooled reactors [J] . P.L.Kirillov Thermal engineering . 2001,第12期

机译：转换为超临界参数：采用水冷堆推进核电站的方式
4. LOSS OF COOLANT ACCIDENT SIMULATION WITH RELAP5/SCDAPSIM/MOD4 FOR THE CANADIAN SUPERCRITICAL WATER-COOLED REACTOR [C] . M. Lou, D. Novog, C. Allison, Annual conference of the Canadian Nuclear Society;CNS/CNA student conference . 2016

机译：加拿大超临界水冷反应器的RELAP5 / SCDAPSIM / MOD4冷却剂事故模拟损失
5. Development of a heat-transfer correlation for supercritical water in supercritical water-cooled reactor applications. [D] . Mokry, Sarah. 2009

机译：超临界水冷反应堆应用中超临界水传热相关性的发展。
6. Development of an automatedchemistry control system forsecondary coolant circuits inCANDU nuclear power reactors [O] . J. R. Dean, R. B. Stewart 1979

机译：开发自动化化学控制系统二次冷却液回路坎杜核电反应堆
7. Figure 1 from: Kirillov PL, Bogoslovskaya GP (2019) Generation IV supercritical water-cooled nuclear reactors: Realistic prospects and research program. Nuclear Energy and Technology 5(1): 67-74. https://doi.org/10.3897/nucet.5.34293 [O] . Pavel L. Kirillov, Galina P. Bogoslovskaya 2019

机译：图1来自：Kirillov Pl，Bogoslovskaya GP（2019）代IV超临界水冷核反应堆：现实主义的前景和研究计划。核能和技术5（1）：67-74。 https://doi.org/10.3897/nucet.5.34293

Prospects for Development of an Innovative Water-Cooled Nuclear Reactor for Supercritical Parameters of Coolant

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