Utilization of SRAC Computer Code as a Nuclear Fuel Management Tool for Thai Research Reactor (TRR-1/M1)
Creators
- Tippayakul, Chanatip1
- Saengchantr, Dhanaj1
- Thailand Institute of Nuclear Technology (Thailand)
- Ministry of Science and Technology (Thailand)
- Office of Atoms for Peace (Thailand)
- Electrticity Generating Authority of Thailand (Thailand)
- Nuclear Society of Thailand (Thailand)
- Department of Agriculture (Thailand)
- Hydro and Agro Informatics Institute (Thailand)
- Department of Livestock Development (Thailand)
- Nuclear Medicine Society of Thailand (Thailand)
- 1. Research Reactor Management Division, Thailand Institute of Nuclear Technology, Bangkok (Thailand)
Description
Full text: An upgrade of fuel management methodology for TRR-1/M1 is presented in this paper. The advanced code system called SRAC is applicable to hexagonal arrangement reactor core thus it is applicable for TRR-1/M1 as a fuel management tool. The methodology is executed in 2 steps, namely hyperfine group structure cross section generation step and reactor core calculation step by applied SRAC's capabilities to create group cross section in to four group structure. For verification purpose, the TRR-1/M1 core configuration number 1 is modeled by the new methodology in this paper. The result of the core excess reactivity of this core shows good agreement with the operation data from operation log-book. This methodology is expected to be employed as a fuel management tool for TRR-1/M1 in the near future
Availability note (English)
Available in abstract form only, full text entered in this record. Available from Thailand Institute of Nuclear Technology, Bangkok (Thailand)Additional details
Publishing Information
- Imprint Pagination
- 12 p.
- Report number
- INIS-TH--167
Conference
- Title
- 10. Conference on Nuclear Science and Technology
- Dates
- 16-17 Aug 2007
- Place
- Bangkok (Thailand)
INIS
- Country of Publication
- Thailand
- Country of Input or Organization
- Thailand
- INIS RN
- 40048209
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Numerical Data, Non-conventional Literature
- Descriptors DEI
- COMPUTER CODES; EXPERIMENTAL DATA; FUEL MANAGEMENT; REACTOR CORES; TRIGA-2 REACTOR
- Descriptors DEC
- DATA; ENRICHED URANIUM REACTORS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; INFORMATION; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MANAGEMENT; NUCLEAR MATERIALS MANAGEMENT; NUMERICAL DATA; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; THERMAL REACTORS; TRIGA TYPE REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- NST--10-ET16