Published August 2017 | Version v1
Miscellaneous Open

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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Part of:
Proceedings of the seminar on nuclear safety 2017: Development of nuclear power oversight based on public information and communication technology

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)

Optional Information

Notes
10 refs.; 5 tabs.; 3 figs. Imprint:Prosiding seminar keselamatan nuklir 2017: Pengembangan pengawasan ketenaganukliran berbasis teknologi informasi dan komunikasi publik