The high temperature isolation valve (HTIV) is a key component to assure the safety of a high temperature gas cooled reactor connected with a hydrogen production system for protections of radioactive material release from the reactor to the hydrogen production system as well as of combustible gas ingress to the reactor at the accident of fracture of an intermediate heat exchanger and the chemical reactor. However, the HTIV has not been made for practical use in the helium condition over yet. The conceptual structure design of an angle type HTIV was carried out. A seat made of Hasteloy-XR is welded inside a valve box. Internal thermal insulation is employed around the seat and a liner because the high temperature helium gas flows inside the valve. The inner diameter of the top of seat was set 445 mm based on fabrication experiences of valve makers. A draft overall structure was proposed based on the diameter of the seat. The numerical analysis was carried out to estimate the temperature distribution and stress of metallic components by using a three-dimensional finite element method code. Numerical results showed that the temperature of the seat was simply decreased from the top around to the root, and the thermal stress locally increased at the root of the seat, which was connected with the valve box. The stress was lowered below the allowable limit 120 MPa by decreasing the thickness of the connecting part and increasing the temperature of the valve box to around . The stress also increased at the top of the seat. Creep analysis revealed that the intactness of the HTIV is kept after the assumed operation cycles of the plant life as well as at the depressurization accident.
Skip Nav Destination
e-mail: takada.shoji@jaea.go.jp
e-mail: inagaki.yoshiyuki@jaea.go.jp
Article navigation
November 2011
Technical Briefs
Conceptual Structure Design of High Temperature Isolation Valve for High Temperature Gas Cooled Reactor
Shoji Takada,
Shoji Takada
Small-Sized HTGR Research and Development Division, Nuclear Hydrogen and Heat Application Research Center,
e-mail: takada.shoji@jaea.go.jp
Japan Atomic Energy Agency (JAEA)
, Oarai, Higashi-ibaraki-gun, Ibaraki 311-1393, Japan
Search for other works by this author on:
Kenji Abe,
Kenji Abe
Frontier System Co. Ltd.
, Mito-shi, Ibaraki 310, Japan
Search for other works by this author on:
Yoshiyuki Inagaki
Yoshiyuki Inagaki
Hydrogen Application Research and Development Division, Nuclear Hydrogen and Heat Application Research Center,
e-mail: inagaki.yoshiyuki@jaea.go.jp
JAEA
, Oarai, Higashi-ibaraki-gun, Ibaraki 311-1393, Japan
Search for other works by this author on:
Shoji Takada
Small-Sized HTGR Research and Development Division, Nuclear Hydrogen and Heat Application Research Center,
Japan Atomic Energy Agency (JAEA)
, Oarai, Higashi-ibaraki-gun, Ibaraki 311-1393, Japane-mail: takada.shoji@jaea.go.jp
Kenji Abe
Frontier System Co. Ltd.
, Mito-shi, Ibaraki 310, Japan
Yoshiyuki Inagaki
Hydrogen Application Research and Development Division, Nuclear Hydrogen and Heat Application Research Center,
JAEA
, Oarai, Higashi-ibaraki-gun, Ibaraki 311-1393, Japane-mail: inagaki.yoshiyuki@jaea.go.jp
J. Eng. Gas Turbines Power. Nov 2011, 133(11): 114501 (3 pages)
Published Online: May 17, 2011
Article history
Received:
October 26, 2010
Revised:
December 28, 2010
Online:
May 17, 2011
Published:
May 17, 2011
Citation
Takada, S., Abe, K., and Inagaki, Y. (May 17, 2011). "Conceptual Structure Design of High Temperature Isolation Valve for High Temperature Gas Cooled Reactor." ASME. J. Eng. Gas Turbines Power. November 2011; 133(11): 114501. https://doi.org/10.1115/1.4003454
Download citation file:
88
Views
Get Email Alerts
Cited By
Research on Effect of Endwall Contouring of Vaned Diffuser on Stable Operating Range of Centrifugal Compressor
J. Eng. Gas Turbines Power (March 2025)
Data-Driven Generative Model Aimed to Create Synthetic Data for the Long-Term Forecast of Gas Turbine Operation
J. Eng. Gas Turbines Power (March 2025)
Optimization of Smooth Straight-Through Labyrinth Seal Based on XGBoost and Improved Genetic Algorithm
J. Eng. Gas Turbines Power (March 2025)
Related Articles
An Evaluation of Creep-Fatigue Damage for the Prototype Process Heat Exchanger of the NHDD Plant
J. Pressure Vessel Technol (October,2011)
An Improved Analytical Method for Life Prediction of Bolting
J. Pressure Vessel Technol (February,2001)
Extension of Fatigue Exemption Rules in Section VIII, Division 2 Slightly Into the Creep Regime
J. Pressure Vessel Technol (April,2012)
Life Estimation of Pressurized-Air Solar-Thermal Receiver Tubes
J. Sol. Energy Eng (November,2012)
Related Proceedings Papers
Related Chapters
New Generation Reactors
Energy and Power Generation Handbook: Established and Emerging Technologies
Damage Accumulation in Titanium Matrix Composites Under Generic Hypersonic Vehicle Flight Simulation and Sustained Loads
Thermomechanical Fatigue Behavior of Materials: Second Volume
Division 5—High Temperature Reactors
Online Companion Guide to the ASME Boiler & Pressure Vessel Codes