Published 1999
| Version v1
Book
On merits and possibility of sodium coolant radioactive waste preliminary cleaning of tritium. Assessment for the BR-10 reactor
Creators
- 1. Gosudarstvennyj Nauchnyj Tsentr Rossijskoj Federatsii Fiziko-Ehnergeticheskij Inst. im. akad. A.I.Lejpunskogo, Obninsk (Russian Federation)
Description
The efficiency of sodium coolant preliminary cleaning of tritium by means of cold traps is assessed. The results of analysis realized for the BR-10 reactor primary coolant circuits are taken as an example. Assessment of tritium mass transfer in sodium circuits during the reactor normal operation is made. Basing on the simplified balance equation for tritium in sodium circuits the parameters characterizing sodium cleaning of tritium in each separate circuit are determined. The conclusion is made that the most efficient sodium cleaning of tritium is available in a case of continuous hydrogen supply into sodium and simultaneous cold trap pumping
Abstract (Russian)
Проведена оценка эффективности предварительной очистки от трития натриевого теплоносителя с помощью холодных ловушек. В качестве примера использованы результаты анализа, проведенного для первого контура системы охлаждения реактора БР-10. Выполнена оценка массопереноса трития в натриевых контурах при работе реактора в номинальном режиме. На основе упрощенного балансного уравнения для трития в натриевых контурах определены параметры, характеризующие очистку натрия от трития в каждом контуре отдельно. Сделан вывод о том, что наиболее экономичная очистка натрия от трития достигается при непрерывной подпитке натрия водородом и одновременной прокачке холодной ловушкиAdditional details
Additional titles
- Original title (Russian)
- О целесообразности и возможности предварительной очистки RAO натриевого теплоносителя от трития. Оценки для реактора BR-10
Publishing Information
- Publisher
- Gosudarstvennyj Nauchnyj Thentr Rossijskoj Federatsii Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov
- Imprint Place
- Dimitrovgrad (Russian Federation)
- ISBN
- 5-85165-377-9
- Imprint Title
- 30 years of the BOR-60 reactor facility operation. Collection of the seminar abstracts
- Imprint Pagination
- 48 p.
- Journal Page Range
- p. 35-36
Conference
- Title
- 30 years of the BOR-60 reactor facility operation
- Original Conference Title
- 30 let ehkspluatatsii reaktornoj ustanovki BOR-60
- Dates
- 8-9 Dec 1999
- Place
- Dimitrovgrad (Russian Federation)
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- Russian Federation
- INIS RN
- 32043951
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COOLANT CLEANUP SYSTEMS; COOLANTS; DECONTAMINATION; DIFFERENTIAL EQUATIONS; EFFICIENCY; LIQUID METALS; MASS TRANSFER; PRIMARY COOLANT CIRCUITS; SBR-5 REACTOR; SODIUM; TRITIUM
- Descriptors DEC
- ALKALI METALS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; BREEDER REACTORS; CLEANING; COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; EPITHERMAL REACTORS; EQUATIONS; FAST REACTORS; FBR TYPE REACTORS; FLUIDS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; LIQUID METAL COOLED REACTORS; LIQUIDS; LMFBR TYPE REACTORS; METALS; NUCLEI; ODD-EVEN NUCLEI; PLUTONIUM REACTORS; PRIMARY COOLANT CIRCUITS; RADIOISOTOPES; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; TEST FACILITIES; TEST REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 1 tab. Imprint:30 let ehkspluatatsii reaktornoj ustanovki BOR-60. Sbornik referatov seminara