Published 1999 | Version v1
Book

Calculated values of neutron-physical characteristics of the BOR-60 reactor

Description

The software complex used for calculational and experimental investigations realized in the BOR-60 reactor experimental facilities is briefly described. Peculiarities of the computer codes applied for calculation of the reactor core and experimental channels neutron-physical characteristics are discussed. The conclusion on good agreement between calculated and experimental values is made. It assures the capabilities for application of the calculational methods in the most during irradiation of samples

Part of:
Methodological provisions of reactor materials testing. Collection of the seminar abstracts

Additional details

Additional titles

Original title (Russian)
Расчетные значения нейтронно-физических характеристик реактора BOR-60

Publishing Information

Publisher
GNTh RF NIIAR
Imprint Place
Dimitrovgrad (Russian Federation)
ISBN
5-85165-373-6
Imprint Title
Methodological provisions of reactor materials testing. Collection of the seminar abstracts
Imprint Pagination
99 p.
Journal Page Range
p. 83-85

Conference

Title
Methodological provisions of reactor materials testing
Original Conference Title
Metodicheskoe obespechenie reaktornogo materialovedeniya
Dates
30-31 Mar 1999
Place
Dimitrovgrad (Russian Federation)

Optional Information

Notes
1 tab. Imprint:Metodicheskoe obespechenie reaktornogo materialovedeniya. Sbornik referatov seminara