Design of High Temperature
Engineering Test Reactor(HTTR)


September 1994

TITLE FILE NAME SIZE(KB)
Cover cover.pdf 74KB
Abstruct abstruct.pdf 140KB
Contents contents.pdf 579KB
Abbreviation abbrevi.pdf 204KB
List of Tables tablelist.pdf 239KB
list of Figures figurelist.pdf 857KB
Executive Summary executive.pdf 860KB
1. GENERAL INTRODUCTION sec1.pdf 1,512KB
@1.1 Preface | |
@1.2 General Philosophy and Specific
Aspect of the HTTR Design
| |
@ 1.2.1 @Basic Principles | |
@ 1.2.2 @Detail Explanation of Reactor Shutdown | |
@ 1.2.3 @Detail Explanation of Residual Heat Removal | |
@ 1.2.4 @Detail Explanation Multiple Barriers
@to FP Release
| |
@1.3 Major Chracteristics of the HTTR | |
2. NUCLEAR DESIGN@@@@ sec2.pdf 2,802KB
@2.1 Summary sec2-1.pdf 179KB
@2.2 Design Requirements sec2-2.pdf 326KB
@2.3 Analytical Method sec2-3.pdf 1,401KB
@ 2.3.1 @Nuclear Design Code System
@and Calculation Method
| |
@ 2.3.2 Validation of Nuclear Design Code System | |@
@2.4 Evaluation Results sec2-4.pdf 1,298KB
@ 2.4.1 Excess Reactivity and Reactor Shutdown Margin | |
@ 2.4.2 Reactivity Addition Rate and Reactivity Coefficients | |
@ 2.4.3 Power Distribution,Burnp and Xenon Spatial Oscillation | |
3. CORE THERMAL AND REACTOR INTERNALS sec3.pdf 1,623KB
@3.1 Summary | |
@3.2 Design Requirements | |
@3.3 Design Details | |
@3.4 Results of R&D | |
@3.5 Evaluation Results@ | |
4. CORE COMPONENTS AND REACTOR INTERNALS | |
@4.1 Summary sec4-1.pdf 369KB
@4.2 Core Components Sec4-2.pdf 2,307KB
@ 4.2.1 @Fuel | |
@ 4.2.2 @Core Components | |
@ 4.2.3 @Graphic Structure Design Guidelines@ | |
@4.3 Reactivity Control System sec4-3.pdf 1,193KB
@ 4.3.1 @Control Rod System | |
@ 4.3.2 @Reserved Shutdown System | |
@4.4 Reactor Internals sec4-4.pdf 1,433KB
@ 4.4.1 @Graphic Core Support Structures | |
@ 4.4.2 @Metallic Core Support Structures | |
@4.5 Reactor Pressure Vessel sec4-5.pdf 803KB
5. COOLING SYSTEM | |
@5.1 Summary sec5-1.pdf 365KB
@5.2 Primary Pressurized Water Cooler | |
@ 5.2.1 @Primary Pressurized Water Cooler sec5-2-1.pdf 1,399KB
@ 5.2.2 @Helium/Helium Intermediate Heat Exchanger | |
@ 5.2.3 @Primary Gas Circulator | |
@ 5.2.4 @Concentric Hot Gas Duct | |
@ 5.2.5 @High Temperature Structual Design Guidelines sec5-2-5.pdf 1,637KB
@5.3 Secondary Helium Cooling System sec5-3.pdf 1304KB
@ 5.3.1 @Secondary Pressurized Water Cooler | |
@ 5.3.2 @Secondary Gas Circulator | |
@ 5.3.3 @Secondary Helium Piping | |
@5.4 Pressurized Water Cooling System | |
@ 5.4.1 @Pressurized Water Pump | |
@ 5.4.2 @Air Cooler | |
@5.5 Residual Heat Removal System | |
@ 5.5.1 @Auxiliary Cooling System | |
@ 5.5.2 @Vessel Cooling System | |
@5.6 Helium Purification System | |
@5.7 Helium Storage and Supply System | |
6. INSTRUMENTATION AND CONTROL SYSTEM sec6.pdf 2,184KB
@6.1 Summary | |
@6.2 Instrumentation System | |
@ 6.2.1 @Reactor Instrumentation | |
@ 6.2.2 @Process Instrumentation | |
@6.3 Contorl System | |
@ 6.3.1 @Operational Mode Selector | |
@ 6.3.2 @Reactor Power Control Device | |
@ 6.3.4 @Plant Dynamic analysis | |
@6.4 Safety Protection System | |
@ 6.4.1 Reactor Protection System | |
@ 6.4.2 Engineered Safety Features Actuating System | |
7. CONTAINMENT STRUCTURES sec7.pdf 350KB
@7.1 Summary | |
@7.2 Reactor Containment Vessel | |
@7.3 Service Area | |
@7.4 Emergency Air Purification System | |
8. OTHER FACILITIES sec8.pdf 2,034KB
@8.1 Fuel Handing and System | |
@ 8.1.1 @Fule Handing System | |
@ 8.1.2 @Fuel Strage System | |
@8.2 Radioactive Waste Treatment System | |
@ 8.2.1 @Gaseous Radwaste Treatment System | |
@ 8.2.2 @Liquid Radwaste Trearment System | |
@ 8.2.3 @Solid Radwaste Treatment System | |
@8.3 Radiation Management System | |
@8.4 Electric Facility@ | |
@8.5 Auxiliary Plant Facilities | |
@ 8.5.1 @Ventilation and Air Conditioning System | |
@ 8.5.2 @Miscellaneous Facilities | |
9. RADIATION PROTECTION sec9.pdf 1,166KB
@9.1 Summary | |
@9.2 Shielding Design | |
@ 9.2.1 @Design Dose Rates | |
@ 9.2.2 @Source Data | |
@ 9.2.3 @Evaluation Results of Shielding
@Design
| |
@9.3 Off-site Exposure during Normal Operation | |
10. TESTS PLANNED IN HTTR sec10.pdf 572KB
@10.1 Summary | |
@10.2 Safety Demonstration Tests | |
@ 10.2.1 @Test Items and Objective | |
@ 10.2.2 @Design Requirement | |
@ 10.2.3 @Operational Restriction | |
@10.3 Irradiation Test | |
11. SEISMIC DESIGN AND SUPPORTING GROUND sec11.pdf 1,185KB
@11.1 Summary | |
@11.2 Seismic Design | |
@ 11.2.1 @Basic Guideline of Seismic
@Design
| |
@ 11.2.2 @Seismic Classification | |
@ 11.2.3 @Basic Design Earthquake Ground
@Motions
| |
@11.3 Geological Composition and Ground Condition | |
@ 11.3.1 @Geological Composition | |
@ 11.3.2 @Stabilityof Supporting Ground | |
12. SAFETY EVALUTION | |
@12.1 Summary sec12-1.pdf @176KB
@12.2 Criteria for Judgemnet sec12-2.pdf @549KB
@ 12.2.1 @Criteria for AOOs | |
@ 12.2.2 @Criteria for Accidents | |
@12.3 Selection of Postulated Events sec12-3.pdf @753KB
@ 12.3.1 @Process of Event Selection | |
@ 12.3.2 @Postulated Events | |
@12.4 Computer Codes Used in Safety Analysis sec12-4.pdf 2,168KB
@ 12.4.1 @BLOOST-J2 Code | |
@ 12.4.2 @THYDE-HTGR Code | |
@ 12.4.3 @TAC-NC Code | |
@ 12.4.4 @RATSAM6 Code | |
@ 12.4.5 @COMPARE-MOD1 Code | |
@ 12.4.6 @GRACE Code | |
@ 12.4.7 @OXIDE-3F Code | |
@ 12.4.8 @FLOWNET/TRUMP Code | |
@12.5 Major Analytical Condition sec12-5.pdf 1,143KB
@ 12.5.1 @Considerations for Operation
@Conditions
| |
@ 12.5.2 @Assumption of Single Failure | |
@ 12.5.3 @Initial Condition of Normal
@Operation
| |
@ 12.5.4 @Characteristics of Reactor
@Protection System
| |
@ 12.5.5 @Characteristics of Reactor
@Scram
| |
@ 12.5.6 @Reactivity Coefficients | |
@ 12.5.7 @Decay Heat | |
@12.6 Analysis of Anticipated Operational Occurrences | |
@ 12.6.1 @Abnormal CR Withdrawal
@during Subcritical Condition
@
sec12-6-1.pdf 1,067KB
@ 12.6.2 @Abnormal CR Withdrawal
@during Rated Power Operation
| |
@ 12.6.3 @Decrease in Primary Coolant
@Flow Rate
| |
@@12.6.3.1 @@Stop of PGC for IHX | |
@@12.6.3.2 @@Opening of exhaust value of
@@primary helium storage and
@@supply system
| |
@ 12.6.4 @Increase in Primary Coolant Flow
@Rate
sec12-6-4.pdf 791KB
@@12.6.4.1 @@ncrease in revolution of PGC
@@for IHX
| |
@@12.6.4.2 @@Increase in revolution of PGC
@@for PPWC
| |
@@12.6.4.3 @@Opening of supply valve of
@@primary helium storage and
@@supply system
| |
@ 12.6.5 @Decrease in Heat Removal by
@Secondary Cooling System
@
sec12-6-5.pdf 948KB
@@12.6.5.1 @@Opening of bypass flow control
@@valve of air cooler
| |
@@12.6.5.2 @@Opening of exhaust valve of
@@secondary helium storage and
@@supply system
| |
@ 12.6.6 @Increase in Heat Removal@by Secondary Colling System sec12-6-6.pdf 411KB
@ 12.6.7 @Loss of Off-site Electric Power sec12-6-7.pdf 840KB
@ 12.6.8 @Transient during Irradiation Test sec12-6-8.pdf 380KB
@@12.6.8.1 @@Abnormal reactivity insertion
@@by movement of irradiation
@@specimen
| |
@@12.6.8.2 @@Deterioration of insulation
@@material in irradiation
@@specimen
| |
@ 12.6.9 @Transient during Safety
@Demonstration Test
sec12-6-9.pdf 335KB
@12.7 Analysis of Accident | |
@ 12.7.1 @Channel Blockage of Standard
@Fuel Element
@
sec12-7-1.pdf 598KB
@ 12.7.2 @Failure of Inner Pipe in
@Primary Consentric Hot
@Gas Duct
| |
@ 12.7.3 @Failure of Inner Pipe in
@Secondary Consentric
@Hot Gas Duct
sec12-7-3.pdf 1,008KB
@ 12.7.4 @Rupture of Secondary
@Concentric Hot Gas Duct
| |
@ 12.7.5 @Rupture of Pipe in PWCS | |
@ 12.7.6 @Depressurization Accident
@(Rupture of Primary Concentric
@Hot Gas Duct)
sec12-7-6.pdf 949KB
@ 12.7.7 @Rupture of PPWC Heat
@Transfer Tube
sec12-7-7.pdf 680KB
@ 12.7.8 @Failure of Primary Helium
@Purification System
| |
@ 12.7.9 @Failure of Gasous Radwaste
@Treatment System
| |
@12.7.10 @Failure of Sweep Gas Pipe
@in Irradiation Test Equipment
sec12-7-10.pdf 1,320KB
@12.7.11 @Channel Blockage of Fuel Failure
@Test Specimen
| |
@12.7.12 @Rupture of Stand Pipe | |
@12.8 Major and Hypothetical Accidents | |
@ 12.8.1 @Major Accident | |
@ 12.8.2 @Hypothetical Accident | |
13. AFTERWORD sec13.pdf 114KB
Ackowledgement | |

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