scholarly journals An evaluation of alternative reactor vessel cutting technologies for the experimental boiling water reactor at Argonne National Laboratory

1989 ◽  
Author(s):  
L.E. Boing ◽  
D.R. Henley ◽  
W.J. Manion ◽  
J.W. Gordon
Keyword(s):  
National Laboratory ◽  
Argonne National Laboratory ◽  
Reactor Vessel ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Water Reactor

ICONE15-10818 Phased Array UT Application for Boiling Water Reactor Vessel Bottom Head

2007 ◽  
Vol 2007.15 (0) ◽  
pp. _ICONE1510-_ICONE1510
Author(s):  
Yasuhiro Yuguchi ◽  
Taiji Hirasawa ◽  
Koji Murakami ◽  
Satoshi Nagai ◽  
Tooru Ootsubo ◽  
...  
Keyword(s):  
Phased Array ◽  
Reactor Vessel ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Water Reactor ◽  
Vessel Bottom

Shift and Adjusted Reference Temperature for a Boiling Water Reactor Vessel

1999 ◽  
Vol 133 (2) ◽  
pp. 213-217
Author(s):  
L. C. Longoria ◽  
J. C. Palacios ◽  
J. Santos
Keyword(s):  
Reactor Vessel ◽  
Boiling Water ◽  
Reference Temperature ◽  
Boiling Water Reactor ◽  
Water Reactor

Effect of External Cooling on the Thermal Behavior of a Boiling Water Reactor Vessel Lower Head

1994 ◽  
Vol 108 (2) ◽  
pp. 266-282 ◽  
Author(s):  
Hyunjae Park ◽  
V. K. Dhir ◽  
William E. Kastenberg
Keyword(s):  
Thermal Behavior ◽  
Reactor Vessel ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Water Reactor ◽  
External Cooling ◽  
Lower Head

Probabilistic Fracture Mechanics Analysis of Boiling Water Reactor Vessel on Relatively Low Failure Probability Problem Using PROFAS-RV PFM Analysis Code

2017 ◽  
Author(s):  
Jongmin Kim ◽  
Bongsang Lee
Keyword(s):  
Stress Intensity ◽  
Fracture Mechanics ◽  
Failure Probability ◽  
Reactor Vessel ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Water Reactor ◽  
Probabilistic Fracture Mechanics ◽  
Ni Content ◽  
Shift Model

The PFM approach has been widely used to evaluate the integrity of reactor pressure vessel (RPV) in nuclear power plant. Since the 1980s, a number of probabilistic fracture mechanics (PFM) analysis codes have been developed to perform the probabilistic analysis for RPV, and these codes are continuously updated by reflecting recent irradiation shift model, database of fracture toughness and compendia of stress intensity factors. The author developed a PFM analysis program for RPV, PROFAS-RV (PRObabilistic Failure Analysis System for Reactor Vessel), recently, which can evaluate failure probability of RPV using recent RTNDT shift model of 10CFR50.61a and stress intensity factor calculation method of RCC-MRx A16 code as well as required basic functions of PFM program. In this paper, the failure probabilities of boiling water reactor (BWR) for cool-down and low temperature over pressurization (LTOP) transient are calculated by using the own PFM analysis code, PROFAS-RV. This work was conducted as part of an international collaborative study. The effects of key parameters such as transient, fluence level, Cu and Ni content, initial RTNDT and RTNDT shift model on the failure probability are systematically compared and reviewed. As expected, the failure probability increases with increasing fluence, Cu and Ni contents, and initial RTNDT. However, the effect of Cu and Ni content is negligible for the very low fluence of 0.02×1019 n/cm2 because there is no additional irradiation embrittlement. The effect of initial RTNDT on the failure probability is more significant for the lower fluence region in both transients. The failure probability of LTOP transient is lower than that of cool-down transient, and the probability of failure with irradiation shift model of 10CFR50.61a is larger than that of R.G.-1.99 rev. 2 at the fluence ranges 0.2×1019 n/cm2 to 0.5×1019 n/cm2.

Concept of a High Pressure Boiling Water Reactor, HP-BWR

2009 ◽  
Author(s):  
Frigyes Reisch ◽  
Hernan Tinoco
Keyword(s):  
High Pressure ◽  
Reactor Vessel ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Large Space ◽  
Water Release ◽  
Pressurized Water ◽  
Water Reactor ◽  
Water Reactors ◽  
Control Rods

Some four hundred Boiling Water Reactors (BWR) and Pressurized Water Reactors (PWR) have been in operation for several decades. The presented concept, the High Pressure Boiling Water Reactor (HP-BWR) makes use of the operating experiences. HP-BWR combines the advantages and leaves out the disadvantages of the traditional BWRs and PWRs by taking in consideration the experiences gained during their operation. The best parts of the two traditional reactor types are used and the troublesome components are left out. HP-BWR major benefits: 1. Safety is improved; -Gravity operated control rods -Large space for the cross formed control rods between fuel boxes -Bottom of the reactor vessel without numerous control rod penetrations -All the pipe connections to the reactor vessel are well above the top of the reactor core -Core spray is not needed -Internal circulation pumps are used. 2. Environment friendly; -Improved thermal efficiency, feeding the turbine with ∼340°C (15 MPa) steam instead of ∼285°C (7MPa) -Less warm water release to the recipient and less uranium consumption per produced kWh and consequently less waste is produced. 3. Cost effective, simple; -Direct cycle, no need for complicated steam generators -Steam separators inside the reactor vessel, and steam dryers together with additional separators can be installed inside or outside the containment -Simple dry containment.

Boiling Water Reactor Plant Analyzer Development at Brookhaven National Laboratory

1986 ◽  
Vol 92 (1) ◽  
pp. 144-156
Author(s):  
H. S. Cheng ◽  
W. Wulff ◽  
A. N. Mallen ◽  
S. V. Lekach ◽  
A. Stritar ◽  
...  
Keyword(s):  
National Laboratory ◽  
Brookhaven National Laboratory ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Reactor Plant ◽  
Water Reactor

Age-related degradation of boiling water reactor vessel internals

1992 ◽  
Vol 133 (1) ◽  
pp. 49-62 ◽  
Author(s):  
A.G Ware ◽  
V.N Shah
Keyword(s):  
Reactor Vessel ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Water Reactor ◽  
Age Related
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