Published September 2000 | Version v1
Miscellaneous

Determination Of Maximum Power Of The RSG-Gas At Power Operation Mode Using One Line Cooling System

  • 1. Center for Development of Research Reactor Technology, National Nuclear Energy Agency, Serpong (Indonesia)

Description

In the frame of minimizing the operation-cost, operation mode using one line cooling system is being evaluated. Maximum reactor power shall be determined to assure that the existing safety criteria are not violated. The analysis was done by means of a core thermal hydraulic code, COOLOD-N. The code solves core thermal hydraulic equation at steady state conditions. By varying the reactor power as the input, thermal hydraulic parameters such as fuel cladding and fuel meat temperatures as well as safety margin against flow instability were calculated. Imposing the safety criteria to the results, maximum permissible power for this operation was obtained as much as 17.1 MW. Nevertheless, for operation the maximum power is limited to 15MW

Part of:
Proceedings of the Seminar on Nuclear Science and Technology: The Role of Nuclear Science and Technology on Empowering National Potential

Additional details

Additional titles

Original title (Indonesian)
Penentuan Daya Maksimum RSG-GAS Pada Moda Operasi Daya Dengan Satu Jalur Sistem Pendingin

Publishing Information

Publisher
Center for Research and Development of Nuclear Techniques, National Nuclear Energy Agency
Imprint Place
Bandung (Indonesia)
Imprint Title
Proceedings of the Seminar on Nuclear Science and Technology: The Role of Nuclear Science and Technology Emporing National Potential
Imprint Pagination
651 p.
Journal Page Range
p. 157-166
ISSN
1410-1769

Conference

Title
Conference on the Role of Nuclear Science and Technology on Empowering National Potential
Original Conference Title
Prosiding Seminar Sains dan Teknologi Nuklir Dalam Pemberdayaan Potensi Nasional
Dates
11-12 Jul 2000
Place
Bandung (Indonesia)

INIS

Country of Publication
Indonesia
Country of Input or Organization
Indonesia
INIS RN
34084841
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COOLING SYSTEMS; HEAT EXCHANGERS; OPERATION; POWER; PROGRAMMING; SAFETY
Descriptors DEC
ENERGY SYSTEMS

Optional Information

Notes
6 refs.; 2 tabs.; 4 figs.