Abstract

The value of βeff for Training Research Isotopes of General Atomics (TRIGA) Mark III reactor, belonging to the National Institute of Nuclear Researches (ININ), is reported. The TRIGA Mark III reactor core was simulated with MCNP6 to deduce the effective multiplication factor (keff) for critical state and after a small insertion of positive reactivity (∼0.20 $). To perform more realistic simulations, we had to incorporate in the composition of the low-enrichment uranium (LEU) fuel element the produced poisons in a time period of six years, considering the operation time in days, during which the reactor was operating at maximum power (1 MWth). The calculation of the βeff value was obtained with the keff results, calculated with the code, and the reactor periods measured experimentally. We also obtained directly the βeff value, through the card of MCNP6 to calculate keff (KOPTS) card of the MCNP6 code in order to compare both values.

References

References
1.
Morse
,
P.
, and
Feshbach
,
H.
,
1953
,
Methods of Theoretical Physics
, Vol.
1
,
McGraw-Hill
, New York, pp.
492
501
.
2.
Glasstone
,
S.
, and
Sesonske
,
A.
,
1994
,
Nuclear Reactor Engineering
, Vol.
1
,
Chapman & Hall
, New York, pp.
238
262
.
3.
Reed
,
A.
,
2007
, “
Medical Physics Calculations With MCNP: A Primer
,”
Summer American Nuclear Society Meeting
, Boston, MA, June 25–28, pp.
4
147
.
4.
General Atomic Division of General Dynamics
,
1965
, “
TRIGA Mark III Reactor Hazard Analysis for Comisión Nacional de Energía Nuclear
,” General Atomic Division of General Dynamics, Mexico City, Mexico, Chap. 5, pp. 5.1–5.30.
5.
Flores
,
N. C.
,
2016
, “
Informe de Seguridad del Reactor TRIGA Mark III del Centro Nuclear
,” IFS, Mexico City, Mexico, Chap.
4
.
6.
Galicia-Aragón
,
J.
,
2016
, “
Estimation of the Fast Neutron Fluence in Laguna Verde RPV—Steel Specimens Simulating Its Irradiation in a TRIGA Reactor
,”
Prog. Nucl. Energy
,
88
, pp.
264
276
.10.1016/j.pnucene.2015.12.014
7.
Pelowitz
,
D.
,
2011
, “
MCNP6 Users Manual
,” Los Alamos Laboratory, Los Alamos, NM, Report No. LA-CP-11-01708.
8.
TRIGA Reactor Division of General Atomics,
2012
, “
HEU to LEU Conversion of the ININ TRIGA Reactor With As-Built Fuel Data
,” TRIGA Reactor Division of General Atomics, San Diego, CA.
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