This paper studies the radiological consequences resulting from withdrawal of nuclear fuel element (FE) from a core of open pool type reactor during normal operation. The FE withdrawal accident may be occurred due to human error during routine transport of spent FE process or from failure of FE clamp during reactor normal operation. For both cases, the FE will move vertically upward toward pool water surface. In case of accidental failure of fuel clamp, a negative reactivity insertion in the core after FE withdrawal and the reactor will be shutdown. MCNP5 code was used in this study to calculate the radiation dose rate levels in the reactor hall and inside the control room during FE withdrawal. The results show that the operator in control room will receive dose rate lower than permissible dose rate limit when FE reaches at depths more than to 211 cm for vertical FE and at depths more than to 246 cm for horizontal FE.

References

References
1.
Pond
,
R. B.
, and
Matos
,
J. E.
,
1994
, “
Photon Dose Rates From Spent Fuel Assemblies With Relation to Self-Protection
,” International Meeting on Reduced Enrichment for Research and Test Reactors, Paris, France, Sept. 18–21, Paper No.
ANL/RERTR/TM-25
.http://www.rertr.anl.gov/FRRSNF/TM25.PDF
2.
Taniuchi
,
H.
,
2000
, “
Model and Method for Reasonable Shielding Calculation of Spent Fuel Casks
,”
J. Nucl. Sci. Technol.
,
37
(
Suppl. 1
), pp.
334
336
.
3.
Anttila
,
M.
,
1996
, “
Gamma and Neutron Dose Rates on the Outer Surface of the Nuclear Waste Disposal Canisters
,”
VTT Energy
, Espoo, Finland.
4.
Croff
,
A. G.
,
1980
, “User's Manual for the ORIGEN2 Computer Code,” Oak Ridge National Laboratory, Oak Ridge, TN, Technical Report No.
ORNL/Tm-7175
.https://inis.iaea.org/search/search.aspx?orig_q=RN:11560149
5.
X-5 MONTE CARLO TEAM,
2003
, “MCNPTM—A General Monte Carlo N-Particle Transport Code,” Version 5, Vol. 1 & 2, Los Alamos National Laboratory, Los Alamos, NM, Report No.
LA-UR-03-1987
.https://www.nucleonica.com/wiki/images/8/89/mcnpvoli.pdf
6.
Abdelhady
,
A.
,
2013
, “
Radiological Performance of Hot Water Layer System in Open Pool Type Reactor
,”
Alexandria Eng. J
,
52
(
2
), pp.
159
162
.
7.
Abdelhady
,
A.
,
2016
, “
Radiation Dose Distributions Due to Sudden Ejection of Cobalt Device
,”
Appl. Radiat. Isotopes
,
115
, pp.
208
211
.
8.
INVAP SE,
1999
, “FSAR: Final Safety Analysis Report,” INVAP SE, Bariloche, Argentina, Technical Report No. 0767-5325-3IBLI-001-1A.1.
9.
ANSI,
1992
, “Neutron and Gamma-Ray Fluence-to-Dose Factors,” American Nuclear Society, La Grange Park, IL, Standard No.
ANSI/ANS-6.1.1-1991
.http://www.ans.org/store/item-240179/
10.
International Commission on Radiation Protection
,
1991
,
Recommendations of the International Commission on Radiation Protection
,
Pergamon Press
,
Oxford, UK
.
You do not currently have access to this content.