ANS 19.10 methods for determining neutron fluence in BWR and PWR pressure vessel and reactor internals
Данный раздел/документ содержится в продуктах:
- Техэксперт: Машиностроительный комплекс
- Картотека зарубежных и международных стандартов
- ASTM C1816 Standard Practice for The Ion Exchange Separation of Small Volume Samples Containing Uranium, Americium, and Plutonium Prior to Isotopic Abundance and Content Analysis
- ASTM C1625 Standard Test Method for Uranium and Plutonium Concentrations and Isotopic Abundances by Thermal Ionization Mass Spectrometry
- ASTM C753 REV A Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
- ASTM C696 Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets
- ASTM C1413 Standard Test Method for Isotopic Analysis of Hydrolyzed Uranium Hexafluoride and Uranyl Nitrate Solutions by Thermal Ionization Mass Spectrometry
- ASTM C696 Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets
- ASTM C753 REV A Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
- ASTM C1625 Standard Test Method for Uranium and Plutonium Concentrations and Isotopic Abundances by Thermal Ionization Mass Spectrometry
- 29
- ASTM C1816 Standard Practice for The Ion Exchange Separation of Small Volume Samples Containing Uranium, Americium, and Plutonium Prior to Isotopic Abundance and Content Analysis
- ASTM C1625 Standard Test Method for Uranium and Plutonium Concentrations and Isotopic Abundances by Thermal Ionization Mass Spectrometry
- ASTM C753 REV A Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
- ASTM C696 Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets
- ASTM C1413 Standard Test Method for Isotopic Analysis of Hydrolyzed Uranium Hexafluoride and Uranyl Nitrate Solutions by Thermal Ionization Mass Spectrometry
- ASTM C696 Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets
- ASTM C753 REV A Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
- ASTM C1625 Standard Test Method for Uranium and Plutonium Concentrations and Isotopic Abundances by Thermal Ionization Mass Spectrometry
- 29.040
- ASTM C1816 Standard Practice for The Ion Exchange Separation of Small Volume Samples Containing Uranium, Americium, and Plutonium Prior to Isotopic Abundance and Content Analysis
- ASTM C1625 Standard Test Method for Uranium and Plutonium Concentrations and Isotopic Abundances by Thermal Ionization Mass Spectrometry
- ASTM C753 REV A Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
- ASTM C696 Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets
- ASTM C1413 Standard Test Method for Isotopic Analysis of Hydrolyzed Uranium Hexafluoride and Uranyl Nitrate Solutions by Thermal Ionization Mass Spectrometry
- ASTM C696 Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets
- ASTM C753 REV A Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
- ASTM C1625 Standard Test Method for Uranium and Plutonium Concentrations and Isotopic Abundances by Thermal Ionization Mass Spectrometry
- 29.040.10
- ASTM C1816 Standard Practice for The Ion Exchange Separation of Small Volume Samples Containing Uranium, Americium, and Plutonium Prior to Isotopic Abundance and Content Analysis
- ASTM C1625 Standard Test Method for Uranium and Plutonium Concentrations and Isotopic Abundances by Thermal Ionization Mass Spectrometry
- ASTM C753 REV A Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
- ASTM C696 Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets
- ASTM C1413 Standard Test Method for Isotopic Analysis of Hydrolyzed Uranium Hexafluoride and Uranyl Nitrate Solutions by Thermal Ionization Mass Spectrometry
- ASTM C696 Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets
- ASTM C753 REV A Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
- ASTM C1625 Standard Test Method for Uranium and Plutonium Concentrations and Isotopic Abundances by Thermal Ionization Mass Spectrometry
- ASTM C1816 Standard Practice for The Ion Exchange Separation of Small Volume Samples Containing Uranium, Americium, and Plutonium Prior to Isotopic Abundance and Content Analysis
- ASTM C1816 Standard Practice for The Ion Exchange Separation of Small Volume Samples Containing Uranium, Americium, and Plutonium Prior to Isotopic Abundance and Content Analysis
- ASTM C1816 Standard Practice for The Ion Exchange Separation of Small Volume Samples Containing Uranium, Americium, and Plutonium Prior to Isotopic Abundance and Content Analysis
- ASTM C1625 Standard Test Method for Uranium and Plutonium Concentrations and Isotopic Abundances by Thermal Ionization Mass Spectrometry
- ASTM C753 REV A Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
- ASTM C696 Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets
- ASTM C1413 Standard Test Method for Isotopic Analysis of Hydrolyzed Uranium Hexafluoride and Uranyl Nitrate Solutions by Thermal Ionization Mass Spectrometry
- ASTM C696 Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets
- ASTM C753 REV A Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
- ASTM C753 REV A Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
- ASTM C696 Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets
- ASTM C1413 Standard Test Method for Isotopic Analysis of Hydrolyzed Uranium Hexafluoride and Uranyl Nitrate Solutions by Thermal Ionization Mass Spectrometry
- ASTM C696 Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets
- ASTM C696 Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets
- ASTM C1413 Standard Test Method for Isotopic Analysis of Hydrolyzed Uranium Hexafluoride and Uranyl Nitrate Solutions by Thermal Ionization Mass Spectrometry
- ASTM C1413 Standard Test Method for Isotopic Analysis of Hydrolyzed Uranium Hexafluoride and Uranyl Nitrate Solutions by Thermal Ionization Mass Spectrometry
- ASTM C996 Standard Specification for Uranium Hexafluoride Enriched to Less Than 5 % 235U
- ASTM C1295 Standard Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium Hexafluoride and Uranyl Nitrate Solution
- ASTM E181 Standard Test Methods for Detector Calibration and Analysis of Radionuclides
- ASTM E523 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Copper
- ASTM C1816 Standard Practice for The Ion Exchange Separation of Small Volume Samples Containing Uranium, Americium, and Plutonium Prior to Isotopic Abundance and Content Analysis
- Картотека зарубежных и международных стандартов
American Nuclear Society
methods for determining neutron fluence in BWR and PWR pressure vessel and reactor internals
N 19.10
Annotation
Scope, purpose, and application
This standard provides a procedure for the evaluation of the best-estimate fast (E > 1.0 MeV) neutron f luence in the annular region between the core and the inside surface of the vessel, through the pressure vessel and the reactor cavity, between the top and bottom of the active fuel given the neutron source in the core. This evaluation employs both fast neutron flux computations and measurement data from invessel and cavity dosimetry, as appropriate. The standard applies to both U.S.-designed pressurized water reactors ~PWRs! and boiling water reactors (BWRs)
Автоматический перевод:
методы для определения нейтрона fluence в BWR и камере высокого давления PWR и реакторных внутренностях
Объем, цель и применение
Этот стандарт предоставляет процедуру для оценки наилучшей оценки быстро (E> 1.0 MeV) нейтрон f luence в кольцевом регионе между ядром и внутренней поверхностью судна, через камеру высокого давления и реакторную впадину, между верхом и низом активного топлива, данного нейтронный источник в ядре. Эта оценка использует и быстрые нейтронные вычисления потока и данные об измерении из invessel и дозиметрии впадины, как соответствующие. Стандарт относится к обоим разработанным США водным реакторам, на которые герметизируют, ~PWRs! и реакторы кипящей воды (BWRs)
