ASTM E944-13e1

Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance



NORMA vydaná dňa 1.1.2013


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Informácie o norme:

Označenie normy: ASTM E944-13e1
Dátum vydania normy: 1.1.2013
Počet strán: 8
Približná hmotnosť: 24 g (0.05 libier)
Krajina: Americká technická norma
Kategória: Technické normy ASTM

Kategórie - podobné normy:

Jaderné elektrárny, bezpečnost

Anotácia textu normy ASTM E944-13e1 :

Keywords:
dosimetry, exposure parameters, irradiation damage, least squares, neutron, reactor surveillance, spectrum adjustment ,, ICS Number Code 27.120.20 (Nuclear power plants. Safety)

  1. Scope

1.1 This guide covers the analysis and interpretation of the physics dosimetry for Light Water Reactor (LWR) surveillance programs. The main purpose is the application of adjustment methods to determine best estimates of neutron damage exposure parameters and their uncertainties.

1.2 This guide is also applicable to irradiation damage studies in research reactors.

1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

  2. Referenced Documents

E526

Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Titanium

E910

Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance, E706 (IIIC)

E854

Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance, E706(IIIB)

E853

Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results, E706(IA)

E844

Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706 (IIC)

E706

Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E 706(0)

E705

Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237

E704

Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238

E693

Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA), E 706(ID)

NBSIR 85–3151

Compendium of Benchmark Neutron Fields for Reactor Dosimetry

E1005

Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706 (IIIA)

E1018

Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E706 (IIB)

E2005

Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields

E2006

Guide for Benchmark Testing of Light Water Reactor Calculations

NUREG/CR-5049

Pressure Vessel Fluence Analysis and Neutron Dosimetry

EPRI NP-2188

Development and Demonstration of an Advanced Methodology for LWR Dosimetry Applications

E170

Terminology Relating to Radiation Measurements and Dosimetry

E262

Test Method for Determining Thermal Neutron Reaction Rates and Thermal Neutron Fluence Rates by Radioactivation Techniques

E263

Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Iron

E264

Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Nickel

E265

Test Method for Measuring Reaction Rates and Fast-Neutron Fluences by Radioactivation of Sulfur-32

E266

Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Aluminum

E393

Test Method for Measuring Reaction Rates by Analysis of Barium-140 From Fission Dosimeters

E481

Test Method for Measuring Neutron Fluence Rates by Radioactivation of Cobalt and Silver

E482

Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)

E523

Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Copper

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