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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