Published 1989 | Version v1
Book Metadata-only

Application of RELAP5/MOD2 to design calculations of more passive safety reactors

Creators

  • 1. Dipt. di Costruzioni Meccaniche e Nucleari, 56100 Pisa (Italy)

Description

In the present paper the results of an analysis carried out with reference to BWR natural circulation plants are discussed. The main purpose is the evaluation of the thermal hydraulic performance of innovative reactor concepts in case of accidents. The RELAP5/MOD2 code has been utilized in this context; the adopted nodalizations and the procedure of code application have been qualified through the analysis of available experimental data

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL (United States)
ISBN
0-89448-150-9
Imprint Title
Proceedings of the fifth nuclear thermal hydraulics
Imprint Pagination
492 p.
Journal Page Range
p. 396-402.

Conference

Title
Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit.
Dates
26-30 Nov 1989.
Place
San Francisco, CA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
24011670
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
BWR TYPE REACTORS; DESIGN; EXPERIMENTAL DATA; PLANNING; R CODES; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; SAFETY ANALYSIS; SAFETY ENGINEERING
Descriptors DEC
ACCIDENTS; COMPUTER CODES; DATA; ENRICHED URANIUM REACTORS; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-891103--.