Center for Applied Nuclear Science and Technology - The National Nuclear Energy Agency plans to modify the TRIGA 2000 Bandung Reactor to Bandung Conversion Reactor by replacing standard TRIGA cylindrical fuel with domestic- made plate type fuel. The consequence of this modification plan is that we must modify the transfer cask. An adequate transfer cask is needed so that the radiation exposure emitted from transfer cask is enough low so that the workers, who handling the spent fuel transfer can work safely. The transfer cask was constructed from two concentric cylindrical steel shells with a bolted top cover plate and a welded bottom. The annulus formed by two shells is filled with lead cast, which functions as a gamma shield.. The results of calculations using the ORIGEN2 software for 18 energy groups, 26% fuel element and 1 day decay time, were used as input for the QADS-SCALE-4.3 software. The transfer cask design was chosen with a thickness of 27 cm, an inner diameter of 14 cm, an outer diameter of 68 cm and a height of 140 cm made of lead. The design provided satisfactory shielding capabilities within the limit of the surface dose rates.

1.
Tim LAK PTNBR-BATAN Bandung
, “
Laporan Analisis Keselamatan Akhir Reaktor TRIGA 2000 Bandung
” Revisi 3. Bandung.
2006
2.
L.A.A.
Terremoto
,
C.A.
Zeituni
,
J.A.
Perrotta
,
J.E.R.
da Silva
, “
Gamma-ray spectroscopy on irradiated MTR fuel elements
”,
Nuclear Instruments and Methods in Physics Research A
450
(
2000
)
495
514
3.
M.
Dragusin
, “
ALARA Principle Aplication for Loading Spent Nuclear Fuel Assemblies from Nuclear Research Reactor VVR-S MAGURELEBUCHAREST ROMANIA into Transportation Casks
”,
N. Engineering
, in:
2016
4.
Ahmad Nabill Ab
Rahim
,
Nurhayati Binti
Ramli
,
Tonny
Lanyau
,
Phongsakorn
Prak
,
Mohd Fazli
Zakaria
, “
Fuel Transfer Cask Conceptual Design for Reactor TRIGA PUSPATI (RTP
)”
5.
J.
Bondre
, “
A Complete NUHOMS® Solution for Storage and Transport of High Burnup Spent Fuel
”,
14th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 2004
),
Berlin, Germany
, September 20-24,
2004
, in: 2004, pp.
1
7
6.
L.S.
Romanato
, “
Safe Advantage on Dry Interim Spent Fuel Storage
”,
WM2008 Conference
, February 24-28,
2008
,
Phoenix, AZ
7.
Bapeten
,
Peraturan Kepala Badan Pengawas Tenaga Nuklir Nomor 4 Tahun 2013 Tentang Proteksi Dan Keselamatan Radiasi Dalam Pemanfaatan Tenaga Nuklir -
JDIH-BAPETEN
,
2013
8.
O.W.
Hermann
,
R.M.
Westfall
, “
ORIGEN-S: Scale System Module to Calculate Fuel Depletion
,
Actinide Transmutation, Fission Product Buildup and Decay
,”
1997
9.
M.D.
DeHart
,
S.M.
Bowman
, “
Reactor Physics Methods and Analysis Capabilities in SCALE
”,
Nucl. Technol.
174
(
2011
)
196
213
10.
B.L.
Broadhead
,
Margaret B.
Emmett
, “
QADS: A Multidimensional Point-Kernel Analysis Module
”,
OAK RIDGE NATIONAL LABORATORY
, June
2011
11.
Tim.
Konversi
, “
Desain Dasar Rev-C Indonesia Final
” 11-05-2018
12.
K. A.
Sudjatmi
,
E. P.
Hastuti
,
S.
Widodo
, "
Analisis konveksi alam teras reaktor TRIGA berbahan bakar tipe pelat menggunakan COOLOD-N2
,"
Jurnal. Teknologi Reaktor Nuklir
, vol.
17
, no.
2
, pp.
67
78
,
2015
13.
D.-W.
Lim
,
C.-W.
Lee
,
J.-Y.
Lim
,
D.
Hartanto
, “
On the Particle Swarm Optimization of cask shielding design for a prototype Sodium-cooled Fast Reactor
”,
Nucl. Eng. Technol.
(
2018
)
1
9
14.
IAEA
, “
Optimization Strategies for Cask Design and Container Loading in Long Term Spent Fuel Storage
”,
2006
.
15.
IAEA
, “
Multi Purpose Container Technolgy for Spent Fuel Management
”,
2000
This content is only available via PDF.