Standard Guide for Application of ASTM Evaluated Cross Section Data File

Importancia y uso:

4.1 The ENDF/B library in the United States and similar libraries elsewhere, such as JEFF (23), JENDL (21), and BROND (22), provide a compilation of neutron cross section and other nuclear data for use by the nuclear community. The availability of these excellent evaluations makes possible standardized usage, thereby allowing easy referencing and intercomparisons of calculations. However, as the first ENDF/B files were developed it became apparent that they were not adequate for all applications. This need resulted in the development of the specialized ENDF/B Dosimetry File (17, 25), consisting of activation cross sections important for dosimetry applications. This file was made available worldwide. Later, other “Special Purpose” files were introduced (26). In the ENDF/B-VI compilation (27), dosimetry files no longer appeared as separate evaluation files. The ENDF/B-VII.0 compilation (28) removed most of the reaction-specific covariance files used by the dosimetry community. It kept the covariance files for the “standard cross sections” in a special sub-library, but the covariance data in this sub-library are only provided over the energy range in which each reaction is considered to be a “standard”, and does not include the full energy range required for LWR PVS dosimetry applications. Later updates to the ENDF/B releases added covariance files for some reaction channels but these covariance files were often based solely on calculations and were not representative of the methodology used to derive the underlying ENDF/B cross section. In response to the need for a dosimetry-specific library, the International Atomic Energy Agency convened a Coordinated Research Project (CRP) that drew upon the set of international experts to provide a recommended set of dosimetry cross sections and to compile a set of validation evidence that supported the use of this recommended dataset. This file, the International Reactor Dosimetry and Fusion File (IRDFF) (19, 20), draws upon other national nuclear evaluations and supplements these evaluations with a set of reactions evaluated by expert international groups. The IRDFF library was developed to support the LWR dosimetry application as well as other dosimetry applications that go beyond the scope of this standard and, as part of its development process, it incorporates validation data acquired in reference and standard benchmark neutron fields. Some of the IRDFF supplemental reactions represent material evaluations that are currently being examined by the CSEWG for inclusion within updated ENDF/B evaluations. The supplemental IRDFF evaluations only include the specific reactions of interest to the dosimetry community and not a full material evaluation. The ENDF community requires a complete evaluation before including it in the main ENDF/B evaluated library.

4.2 The application to LWR surveillance dosimetry introduced new data needs that can best be satisfied by the creation of a dedicated cross section file. This file shall be maintained in a form designed for easy application by users (minimal processing). The file shall continue to incorporate the following types of information or indicate the sources of the following type of data that should be used to supplement the file contents:

4.2.1 Dosimetry cross sections for fission, activation, helium production sensor reactions in LWR environments in support of radiometric, solid state track recorder, helium accumulation dosimetry methods (see Test Methods E853, E854, E910, and E1005).

4.2.2 Other cross sections or sensor response functions useful for active or passive dosimetry measurements, for example, the use of neutron absorption cross sections to represent attenuation corrections due to covers or self-shielding.

4.2.3 Cross sections for damage evaluation, such as displacements per atom (dpa) in iron.

4.2.4 Related nuclear data needed for dosimetry, such as branching ratios, fission yields, and atomic abundances.

4.3 The ASTM-recommended cross sections and uncertainties are based mostly on the IRDFF (version 1.05) dosimetry files. Damage cross sections for materials such as iron have been added in order to promote standardization of reported dpa measurements within the dosimetry community. Integral measurements from benchmark fields and reactor test regions have been considered in order to ensure self-consistency (29). The total dosimetry file is intended to be as self-consistent as possible with respect to both differential and integral measurements as applied in LWR environments. This self-consistency of the data file is mandatory for LWR-pressure vessel surveillance applications, where only very limited dosimetry data are available. Where modifications to an existing evaluated cross section have been made to obtain this self-consistence in LWR environments, the modifications shall be detailed in the associated documentation (see (19, 29)).

Subcomité:

E10.05

Referida por:

E0265-15R20, E0720-23, E0721-22, E0393-19, E0266-23, E0263-18, E1297-18, E1006-21, E1035-18R23, E0523-21E01, E0526-22, E1854-19, E0853-23, E0704-19, E2006-22, E0705-18, E0261-16R21, E2956-23, E1005-21, E0910-24, E0264-19, E0944-19, E0482-22, E0706-23

Volúmen:

12.02

Número ICS:

35.240.50 (IT applications in industry)

Palabras clave:

covariance matrix; cross section; dosimetry; ENDF; IRDFF; JEFF; JENDL; nuclear metrology ;