Published 1995 | Version v1
Miscellaneous Metadata-only

Analysis of mixed oxides critical experiments using the Hammer-Technion code with self-shielding treatment by Bondarenko method

Creators

  • 1. Coordenadoria para Projetos Especiais (COPESP), Sao Paulo, SP (Brazil)
  • 2. Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

Description

The present work summarizes the verification of the treatment of self-shielding based on Bondarenko method in HAMMER-TECHNION cell code for the Pu O2-U O2 critical system using JENDL-3 nuclear data library. The results obtained are in excellent agreement with the original treatment of self-shielding employed by HAMMER-TECHNION cell code. (author). 9 refs, 1 fig, 9 tabs

Part of:
Proceedings of the 10. Meeting on Reactor Physics and Thermal Hydraulics

Additional details

Additional titles

Original title (Portuguese)
Analise de experimentos criticos de oxidos mistos utilizando o codigo Hammer-Techion com tratamento de autoblindagem via metodo de Bondarenko

Publishing Information

Imprint Title
Proceedings of the 10. Meeting on Reactor Physics and Thermal Hydraulics
Imprint Pagination
563 p.
Journal Page Range
p. 16-20.

Conference

Title
10. Meeting on Reactor Physics and Thermal Hydraulics.
Original Conference Title
10. Encontro de Fisica de Reatores e Termo-Hidraulica
Dates
7-11 Aug 1995.
Place
Aguas de Lindoia, SP (Brazil).

INIS

Country of Publication
Brazil
Country of Input or Organization
Brazil
INIS RN
27014953
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CERAMICS; CROSS SECTIONS; FISSION; FUEL ASSEMBLIES; FUEL ELEMENTS; H CODES; MIXED OXIDE FUELS; MULTIGROUP THEORY; NEUTRON TRANSPORT THEORY; REACTOR CORES; REACTOR KINETICS; REACTOR PHYSICS; REACTORS; SELF-SHIELDING; SHIELDING
Descriptors DEC
COMPUTER CODES; ENERGY SOURCES; FUELS; KINETICS; MATERIALS; NUCLEAR FUELS; NUCLEAR REACTIONS; REACTOR COMPONENTS; REACTOR MATERIALS; SOLID FUELS; TRANSPORT THEORY

Optional Information

Notes
Imprint:Joint nuclear conference with the 3. Brazilian Meeting on Nuclear Applications.;Anais do 10. Encontro de Fisica de Reatores e Termo-Hidraulica.