RELAP5-3D Assessment Using a Qualified Experimental Database
, 2013 The independent code assessment constitutes an important part in the qualification of an analytical tool for performing licensing or NPP support activities.
Petruzzi, A. +9 more
core +1 more source
RELAP5 modeling of a Savannah River Site reactor [PDF]
, 1990 Thermal-hydraulic system analysis in support of Savannah River Site reactor restart is being performed with a modified version of RELAP5/MOD2.5. This paper gives an overview of the Savannah River Site reactor system, the RELAP5 input models developed for
Dimenna, R.A. (Westinghouse Savannah River Co., Aiken, SC (USA)) +1 more
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Peach Bottom turbine-trip Test 3 analysis with RELAP5 code [PDF]
, 1983 The Peach Bottom turbine trip tests provide excellent benchmark problems for transient analysis of a boiling water reactor (BWR). Analyses of the three turbine trip tests with the RELAP3B/BNL-TWIGL, RETRAN and other codes have been documented.
Lu, M.S.
core
Steam generator identification using piecewise affine model
Results in Nonlinear Analysis, 2019 The role of steam generators in power plants is to remove the thermal power produced in the first cycle and provide the turbine intake steam. Controlling the steam generator water level has an important role in preventing unwanted turbine trips and ...
Samaneh Sadat Sajjadi, Amin Jajarmi, Ahamad Hajipour
doaj
Air-water hydraulics modeling for a Mark-22 fuel assembly with RELAP5: Part 2 [PDF]
, 1991 The RELAP5/MOD2.5 computer program is being used to simulate hypothetical loss-of-coolant accidents in the Savannah River Site (SRS) production reactors.
Caraher, D.L. (Engineering Software Consulting (United States))
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Application of RELAP5 to a pipe blowdown experiment. [PWR; BWR]
, 1980 The application of the RELAP5 computer program to a pipe blowdown experiment is described in this paper. The basic hydrodynamic model, constitutive relations, and special process models included in RELAP5 are also briefly discussed.
Wagner, R. J. +2 more
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Numerical simulation of heat dissipation characteristics in PWR high-pressure coolant pipes during cold shutdown. [PDF]
Sci RepTang F +5 more
europepmc +1 more source
RELAP5/MOD3.2의 강수부 비등 문제 해결 방안 개발
, 2004 학위논문(석사) - 한국과학기술원 : 원자력및양자공학과, 2004.8, [ viii, 71 p. ]Experimental study and RELAP5 analysis have been performed to investigate boiling phenomena in the downcomer with Direct Vessel Injection (DVI), which is a new Safety Injection System (SIS) of ...
박태철, Park, Tae-Chul
core
Adaptive Forecasting of Nuclear Power Plant Operational Status Under Sensor Concept Drift Using a Bridging Distribution Adaptive Network. [PDF]
Sensors (Basel)Xu K +5 more
europepmc +1 more source
Preliminary risk assessment of in-vessel leakage accident in ITER. [PDF]
Sci RepDuan Q +5 more
europepmc +1 more source