The supercritical water reactor (SCWR) fuel qualification test is an in-pile test of a four-rod fuel assembly at supercritical pressure inside a research reactor, which is operated at atmospheric pressure. The risk of radioactive release from this new test facility should not exceed the accepted risk of the existing research reactor. A large number of safety analyses have been performed to assess this risk, which are summarized in this paper. Among them are studies of design basis accidents, assuming different failure modes of the high-pressure system, as well as an assessment of consequences of postulated accidents beyond the design basis. Results show that the safety objectives can be met.
Issue Section:
Research Papers
Topics:
Accidents,
Coolants,
Design,
Fuels,
Pressure,
Safety,
Temperature,
Flow (Dynamics),
Failure,
Heat,
Pumps,
Supercritical water reactors,
Water
References
1.
Schulenberg
, T.
, and Starflinger
, J.
, 2012
, High Performance Light Water Reactor—Design and Analyses
, KIT Scientific Publishing
, Karlsruhe, Germany
.2.
Ruzickova
, M.
, Schulenberg
, T.
, Visser
, D.
, Maraczy
, C.
, Toivonen
, A.
, Kiss
, A.
, and Novotny
, R.
, 2014
, “Overview and Progress in the European Project “Supercritical Water Reactor—Fuel Qualification Test”
,” Prog. Nucl. Energy
, 77
, pp. 381
–389
. 0149-197010.1016/j.pnucene.2014.01.0113.
Raqué
, M.
, 2014
, “Safety Analyses for a Fuel Qualification Test With Supercritical Water
,” Dissertation, Karlsruhe Institute of Technology
, Germany.4.
Raqué
, M.
, Frybort
, O.
, Vojacek
, A.
, and Schulenberg
, T.
, 2013
, “Passive Residual Heat Removal System for the SCWR Fuel Qualification Test Facility
,” 15th International Topical Meeting on Nuclear Reactor Thermalhydraulics
, Pisa, Italy
, NURETH15-112.5.
Schulenberg
, T.
, and Raqué
, M.
, 2014
, “Safety Analyses for an In-Pile SCWR Fuel Qualification Test Loop
,” 19th Pacific Basin Nuclear Conference
, Vancouver, Canada
, PBNC 2014-106.6.
Zhou
, C.
, Yang
, Y.
, and Cheng
, X.
, 2012
, “Feasibility Analysis of the Modified ATHLET Code for Supercritical Water Cooled Systems
,” Nucl. Eng. Des.
, 250
, pp. 600
–612
.7.
Schulenberg
, T.
, Raqué
, M.
, and Arheidt
, K.
, 2013
, “Prediction of Heat Transfer During Depressurization From Supercritical Pressure
,” 15th International Topical Meeting on Nuclear Reactor Thermalhydraulics
, Pisa, Italy
, NURETH15-139.8.
Zeiger
, T.
, Raqué
, M.
, and Schulenberg
, T.
, 2013
, “Study of Consequences of a Pressure Tube Failure for an SCWR In-Pile Fuel Assembly Test
,” 15th International Topical Meeting on Nuclear Reactor Thermalhydraulics
, Pisa, Italy
, NURETH15-207.9.
Zeiger
, T.
, 2014
, “Auswirkungen eines postulierten Druckrohrversagens während des SCWR Fuel Qualification Tests
,” Dissertation, Karlsruhe Institute of Technology
, Germany.10.
Lorenz
, R. A.
, and Osborne
, M. F.
, 1995
, “A Summary of ORNL Fission Product Release Tests With Recommended Release Rates and Diffusion Coefficients
,” Oak Ridge National Laboratory
, Oak Ridge, TN, NUREG/CR-6261.11.
Ishida
, T.
, Harayama
, Y.
, and Yaguchi
, S.
, 1986
, “Oxidation of 304 Stainless Steel in High Temperature Steam
,” J. Nucl. Mater.
, 140
(1
), pp. 74
–84
.10.1016/0022-3115(86)90198-412.
Friedrich
, A. A.
, Veser
, A.
, Stern
, G.
, and Kotchourko
, N.
, 2011
, “Hyper Experiment on Catastrophic Hydrogen Releases Inside a Fuel Cell Enclosure
,” Int. J. Hydrogen Energy
, 36
(3
), pp. 2678
–2687
.10.1016/j.ijhydene.2010.04.00713.
Matějka
, K.
, et al, 2004
, “Requirements of the State Office for Nuclear Safety on Nuclear Research Facilities With Respect to Nuclear Safety, Radiation Protection, Physical Protection and Emergency Preparedness
,” Prague, Czech Republic.Copyright © 2015 by ASME
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