Published 1999
| Version v1
Miscellaneous
Use of safety potential methodology in analysis of self-protection properties of lead-based cooled reactors
- 1. RNTs Kurchatovskij Inst., Moscow (Russian Federation)
Description
The lead-based cooled reactors meet the requirements of the natural safety concept in a higher degree than the reactors of other types. Creation of such reactors should be based on the new methodological basis. The analysis of the reactor safety properties at the early stage of the project is an important feature of this approach. This analysis makes it possible to identify the weakest points in the project and correct them in a timely manner (change in the reactor design and core composition, choice of the parameters and the fuel rod type, accept of the first-circuit parameters, etc). Thus, the self-protection is an inherent feature of the reactor quality
Abstract (Russian)
Реакторы, охлаждаемые теплоносителями на основе свинца, соответствуют требованиям концепции естественной безопасности в гораздо большей степени, чем реакторы других типов. Строительство подобных реакторов должно основываться на новой методологической базе. Важной чертой нового подхода является анализ свойств безопасности реактора на ранней стадии проекта. Этот анализ позволяет обнаружить самые слабые места в проекте и своевременно их исправить (изменить конструкцию и состав активной зоны, выбрать параметры и тип топливного стержня, принять параметры для первого контура и т.д.). Таким образом, самозащищенность является неотъемлемым качеством реактораAdditional details
Additional titles
- Original title (Russian)
- Использование методологии потенциал безопасности при анализе свойств самозащиты реакторов с теплоносителем на основе свинца
Publishing Information
- Publisher
- GNTs RF FEhI
- Imprint Place
- Obninsk (Russian Federation)
- Imprint Title
- Heavy liquid-metal coolants in the nuclear technologies. Collection of reports of the conference in two volumes. Volume 2
- Imprint Pagination
- 824 p.
- Journal Page Range
- p. 576-591
- Report number
- INIS-RU--475
Conference
- Title
- Heavy liquid-metal coolants in the nuclear technologies
- Original Conference Title
- Tyazhelye zhidkometallicheskie teplonositeli v yadernykh tekhnologiyakh
- Dates
- 5-9 Oct 1998
- Place
- Obninsk (Russian Federation)
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- Russian Federation
- INIS RN
- 34075932
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COOLANTS; D CODES; DESIGN; FAST REACTORS; FLOWSHEETS; FUEL RODS; LEAD; LIQUID METAL COOLED REACTORS; LIQUID METALS; OPTIMIZATION; PARAMETRIC ANALYSIS; PRIMARY COOLANT CIRCUITS; RADIATION PROTECTION; REACTOR ACCIDENTS; REACTOR CORES; REACTOR SAFETY; SPECIFICATIONS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; DIAGRAMS; ELEMENTS; ENERGY SYSTEMS; EPITHERMAL REACTORS; FLUIDS; FUEL ELEMENTS; INFORMATION; LIQUIDS; METALS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY
Optional Information
- Notes
- 18 refs., 9 figs., 4 tabs. Imprint:Tyazhelye zhidkometallicheskie teplonositeli v yadernykh tekhnologiyakh. Sbornik dokladov konferentsii v 2-kh tomakh. Tom 2