Published March 2016
| Version v1
Journal article
Steady state and transient analyses of MNSR reactor using RELAP5 code
- 1. Nuclear Science and Technology Research Institute (NSTRI), Tehran (Iran, Islamic Republic of). Reactor Research School
- 2. Islamic Azad Univ., Shiraz (Iran, Islamic Republic of). Dept. of Nuclear Engineering
Description
Developing a reliable thermal-hydraulic model of a nuclear reactor is an essential process in the steady state and transient analyses. This paper provides the results of best estimate calculation carried out with reference to Iranian Miniature Neutron Source Reactor (MNSR) using the RELAP5 code. Applying the qualified nodalization and the cross-flow effects are some of the advantages in the present model. Here, various transients including step and ramp reactivity insertions were inspected for safety analysis. The obtained results from the code showed a reasonable agreement with the MNSR Safety Analysis Report (SAR) and existing experimental and reference data.
Additional details
Publishing Information
- Journal Title
- Kerntechnik (1987)
- Journal Volume
- 81
- Journal Issue
- 1
- Journal Page Range
- p. 25-33
- ISSN
- 0932-3902
- CODEN
- KERNEU
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 47065474
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- MNSR TYPE REACTORS; R CODES; REACTIVITY INSERTIONS; STEADY-STATE CONDITIONS; THERMAL HYDRAULICS; TRANSIENTS
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS