Description of condition at one stuck rod HTR-10 viewed from the shutdown margin value
- 1. Group Riset Nuklir dan Radiasi, FMIPA, Universitas Sebelas Maret, Surakarta (Indonesia)
- 2. Badan Pengawas Tenaga Nuklir (BAPETEN), Jl. Gajah Mada No. 8 Jakarta Pusat 10120 (Indonesia)
Description
Neutronic simulation of HTR-10 has been performed with MVP (Monte Carlo Visual Program) code by JAERI. This code is chosen because it is the most simple to draw up reactor geometry inputs. The MVP code library data is JENDL-3.3, which is filled on the reactor geometry that has been arranged. HTR-10 is a type of a pebble bed reactor, containing uranium oxide spherical ball (UO2) with 17 % enrichment, covered by a layer of TRISO. HTR-10 is modeled using graphite as a moderator and reflector material, helium gas as a coolant material, and control rod is a boron carbide material. HTR-10 is operated at a power of 10 MW with average temperature of helium inlet and outlet is 250 °C and 700 °C, the diameter of core is 1.8 m and the height of core is 1.97 m, containing about 27000 pebbles. This simulation is focused on the variation of control rod position, which at one stuck rod of the 10 control rods is found on the HTR-10. The simulation result is is keff value, so it can be calculated the value of reactivity, ρ and shutdown margin (SDM). The simulation result show that the OSR is obtained by positive reactivity and SDM $1.9215 ± 0.0009. Since the minimum value of SDM is $0.7, according the theoretical of HTR-10 is safe to be shutdown OSR case. (author)
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Additional details
Additional titles
- Original title (Indonesian)
- Deskripsi kondisi at one stuck rod HTR-10 ditinjau dari nilai shutdown margin
Publishing Information
- Publisher
- Nuclear Energy Regulatory Agency
- Imprint Place
- Yogyakarta (Indonesia)
- Imprint Title
- Proceedings of the seminar on nuclear safety 2017: Development of nuclear power oversight based on public information and communication technology
- Imprint Pagination
- 389 p.
- Journal Page Range
- p. 358-362
- ISSN
- 1412-3258
- Report number
- INIS-ID--89
Conference
- Title
- The Seminar on Nuclear Safety 2017
- Original Conference Title
- Seminar Keselamatan Nuklir 2017
- Dates
- 1 Aug 2017
- Place
- Yogyakarta (Indonesia)
INIS
- Country of Publication
- Indonesia
- Country of Input or Organization
- Indonesia
- INIS RN
- 51070192
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; COMPUTERIZED SIMULATION; CONTROL ELEMENTS; HTR-10 REACTOR; MONTE CARLO METHOD; PEBBLE BED REACTORS; REACTOR SHUTDOWN
- Descriptors DEC
- CALCULATION METHODS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HOMOGENEOUS REACTORS; HTGR TYPE REACTORS; REACTOR COMPONENTS; REACTOR LIFE CYCLE; REACTORS; RESEARCH AND TEST REACTORS; SHUTDOWN; SIMULATION; SOLID HOMOGENEOUS REACTORS; TEST FACILITIES; TEST REACTORS
Optional Information
- Notes
- 10 refs.; 5 tabs.; 3 figs. Imprint:Prosiding seminar keselamatan nuklir 2017: Pengembangan pengawasan ketenaganukliran berbasis teknologi informasi dan komunikasi publik