COLD NEUTRON SOURCE AT CMRR

Similar documents
Design Characteristics of the Cold Neutron Source in HANARO Process System and Architecture Design

Irradiation Facilities at the Advanced Test Reactor International Topical Meeting on Research Reactor Fuel Management Lyon, France

THE PRESENT STATUS AND FUTURE POTENTIAL APPLICATIONS OF RRS IN CIAE. 1. BRIEF INTRODUCTION TO RRs IN CIAE AND THEIR UTILIZATION

Application of COMSOL Pipe Flow Module to Develop a High Flux Isotope Reactor System Loop Model

4.2 DEVELOPMENT OF FUEL TEST LOOP IN HANARO

DESIGN AND SAFETY- SUPPORT ANALYSES OF AN IN-PILE MOLTEN SALT LOOP IN THE HFR

OPAL. Australia s Research Reactor. Greg Storr

VVER-440/213 - The reactor core

LOS ALAMOS AQUEOUS TARGET/BLANKET SYSTEM DESIGN FOR THE ACCELERATOR TRANSMUTATION OF WASTE CONCEPT

Status of the FRM-II Project at Garching. Hans-Jürgen Didier, Gunter Wierheim Siemens AG, Power Generation (KWU), D Erlangen

Safety of Experimental Facility in JRR-3

Transient thermal analysis of a cryogenic hydrogen vessel

ESS Target Facility Design. John Haines for the ESS Target Project Team

DETAILED ANALYSIS OF GEOMETRY EFFECT ON TWO PHASE NATURAL CIRCULATION FLOW UNDER IVR-ERVC

Current Status of Research and Development on System Integration Technology for Connection between HTGR and Hydrogen Production System at JAEA

UNIT-5 NUCLEAR POWER PLANT. Joining of light nuclei Is not a chain reaction. Cannot be controlled

GA A22446 DESIGN, FABRICATION AND TESTING OF HELIUM-COOLED VANADIUM MODULE FOR FUSION APPLICATIONS

The Characteristics and Irradiation Capabilities of MARIA research reactor in NCBJ Świerk

Oregon State University s Small Modular Nuclear Reactor Experimental Program

The design features of the HTR-10

Application for Permission to Extend the Operating Period and Application for Approval of Construction Plans of Unit 3 at Mihama Nuclear Power Station

LOSS OF COOLANT ACCIDENT AND LOSS OF FLOW ACCIDENT ANALYSIS OF THE ARIES-AT DESIGN

Evolution of Nuclear Energy Systems

Nuclear Research Institute. Nuclear Research Institute CONTENTS

Current Status and Future Trends in the Development of Russian Research Reactors

Preliminary Lessons Learned from the Fukushima Daiichi Accident for Advanced Nuclear Power Plant Technology Development

The IPNS Grooved, Solid Methane Moderator*

Scenarios of Heavy Beyond-Design-Basis Accidents in HTGRs N.G. Kodochigov, Yu.P. Sukharev

Advanced Instrumentation for Transient Reactor Testing

Operation of the High-Temperature Engineering Test Reactor

UTILIZATION OF ETRR-2 AND COLLABORATION 1. INTRODUCTION

Analysis of water production costs of a nuclear desalination plant with a nuclear heating reactor coupled with MED processes

TOPIC: KNOWLEDGE: K1.01 [2.5/2.5]

Module 05 WWER/ VVER (Russian designed Pressurized Water Reactors)

PUSPATI TRIGA REACTOR UPGRADING: TOWARDS THE SAFE OPERATION & FEASIBILITY OF NEUTRONIC APPROACH

Thermal Response of a High Temperature Reactor during Passive Cooldown under Pressurized and Depressurized Conditions

HTR Research and Development Program in China

JORDAN RESEARCH AND TRAINING REACTOR UTILIZATION FACILITIES

Passive Cooldown Performance of Integral Pressurized Water Reactor

GTT Pluto II Subsea Cryogenic Pipeline

Demonstration Test Program for Long term Dry Storage of PWR Spent Fuel

THE CRYOGENIC SYSTEM FOR THE LHC TEST STRING 2: DESIGN, COMMISSIONING AND OPERATION

IAEA Technical Meeting on Products and Services of Research Reactors 28 June 2 July 2010 IAEA, Vienna, Austria

Earthquake Analysis for Cryogenic Components of NPDG Liquid Hydrogen Target

Heat exchanger equipment of TPPs & NPPs

Status Report and Documentation of DCLL Design

Advanced Sodium Fast Reactor Power Unit Concept

Research and Development Program on HTTR Hydrogen Production System

System Analysis of Pb-Bi Cooled Fast Reactor PEACER

EVALUATION OF RELAP5/MOD3.2 FOR AP1000 PASSIVE RESIDUAL HEAT REMOVAL SYSTEM

THE NEW 10 MW(T) MULTIPURPOSE TRIGA REACTOR IN THAILAND

BN-1200 Reactor Power Unit Design Development

NuScale: Expanding the Possibilities for Nuclear Energy

LABGENE CONTAINMENT FAILURE MODES AND EFFECTS ANALYSIS

Experimental and Analytical Results on H 2 SO 4 and SO 3 Decomposer for IS Process Pilot Plant

The new material irradiation infrastructure at the BR2 reactor. Copyright 2017 SCK CEN

A High Temperature Gas Loop to Simulate VHTR and Nuclear Hydrogen Production System

The "Réacteur Jules Horowitz" : The preliminary design

PRESENT STATUS OF LEGAL & REGULATORY FRAMEWORK AND DECOMMISSIONING PLANNING FOR DNRR. Prepared by NUCLEAR RESEARCH INSTITUTE, VAEC.

Research Reactors Status and Potential Areas of Collaborations in EGYPT

Endless Possibilities Use of Heat Pipe for Global Warming Reduction

Safety in Cryogenics. Cryogen Handling Hazards. Bernd Petersen DESY MKS1 Quellen (u.a):

NSSS Design (Ex: PWR) Reactor Coolant System (RCS)

Test of Abnormal Heat in Hydrogen Loaded Metal

PROBABILISTIC SAFETY ASSESSMENT OF JAPANESE SODIUM- COOLED FAST REACTOR IN CONCEPTUAL DESIGN STAGE

AP1000 European 19. Probabilistic Risk Assessment Design Control Document

Development of Decommissioning Plan in Indonesia

Operation of the Levitated Dipole Experiment Floating Coil

STEAM GENERATOR LEAKAGE AT THE BN-350 DESALINATION PLANT

Supercritical Water-Cooled Reactor (SCWR) Development through GIF Collaboration

LOCA analysis of high temperature reactor cooled and moderated by supercritical light water

NDE Inspections of the NRU Calandria Vessel Part 1: NRU and ET Inspections


Neutron applications laboratory for ESS-BILBAO

Electromagnetic flowmeter, 861 Electromagnetic pumps, 844 characteristics, 845 efficiency, 845 End blanket effects, 869 Energy costs, summary, 921 Eng

2008 JINST 3 S The interface to the LHC machine. Chapter Beampipe Layout

2008 JINST 3 S Cryogenic system. Chapter Overview

NUCLEAR PLANT WITH VK-300 BOILING WATER REACTORS FOR POWER AND DISTRICT HEATING GRIDS

THE ROLE OF A RESEARCH REACTOR IN THE NATIONAL NUCLEAR ENERGY PROGRAMME IN VIETNAM: PRESENT AND FUTURE

PRESENT STATUS OF THE HIGH TEMPERATURE ENGINEERING TEST REACTOR (HTTR)

Lecture (3) on. Nuclear Reactors. By Dr. Emad M. Saad. Mechanical Engineering Dept. Faculty of Engineering. Fayoum University

Evaluation of Two Phase Natural Circulation Flow in the Reactor Cavity under IVR-ERVC for Different Thermal Power Reactors

PLANNING AND MANAGEMENT OF REFURBISHMENT WORK OF CIRUS

This description was taken from the Advances in Small Modular Reactor Technology Developments 2016 Edition booklet.

Molten Salt Reactor Technology for Thorium- Fueled Small Reactors

Reaktor Nuklir Generasi IV

REFURBISHMENT OF THE COOLING SYSTEM OF THE 3 MW TRIGA Mk-II RESEARCH REACTOR OF BANGLADESH

Concept of power core components of the SlimCS fusion DEMO reactor

Accelerator targets design - The challenge of high power density. Ido Silverman DAPNIA visit 24/10/07

PARTIAL SAFETY ANALYSIS FOR A REDUCED URANIUM ENRICHMENT CORE FOR THE HIGH FLUX ISOTOPE REACTOR

NODALIZATION SCHEMES FOR LUMPED-PARAMETER CALCULATIONS OF REPRESENTATIVE NUCLEAR REACTOR SEVERE ACCIDENT TESTS IN THE MISTRA FACILITY

Draft proposals for Test methods for close-coupled solar water heating systems - Reliability and safety

Fast Reactor Operating Experience in the U.S.

Vertically aligned 14 Tesla split-pair

Status of Compatibility Facilities and Experiments on LBE with CLEAR-I Structural Materials

FUKUSHIMA DAIICHI BWR REACTOR SPRAY AND FEED WATER SYSTEMS EVALUATION FOR EARLY FAILURE Dean Wilkie

REACTOR TECHNOLOGY DEVELOPMENT UNDER THE HTTR PROJECT

Characterization of laser-material interaction during laser cladding process P.-A. Vetter,* J. Fontaine,* T. Engel," L. Lagrange,& T.

Overview of ISIS Moderators

Profile SFR-52 SWAT JAPAN. Japan Atomic Energy Agency, 4002 Narita, Oarai-machi, Ibaraki, Japan.

Transcription:

COLD NEUTRON SOURCE AT CMRR Hu Chunming Shen Wende, Dai Junlong, Liu Xiankun ( 1 ) Vadim Kouzminov, Victor Mityukhlyaev / 2 /, Anatoli Serebrov, Arcady Zakharov ( 3 ) ABSTRACT As an effective means to study structure of many materials and law of microcosmic movements on atomic or molecular scale, neutron scattering technique is paid more and more attention by many countries. To promote its development in China, a set of advanced Neutron Scattering Experimental Facility (NSEF) will be installed at China Mianyang Research Reactor (CMRR) under construction. A cold neutron source (CNS), one of the most important components of NSEF, is a mono-phase liquid hydrogen moderator and vertical thermosiphon type. Nice working capacity and safety are the benefit features of CNS at CMRR with a sub-cooled liquid hydrogen thermosiphon. Cooling helium from refrigerator removes the total heat load from CNS in the heat exchanger. In the paper, the in-pile parts, parameters and safety features of CNS are given in detail. At the same time, the utilization of the CNS is briefly described. Keywords: CNS, liquid hydrogen moderator, CNS parameters, CNS utilization 1 Institute of Nuclear Physics and Chemistry of China Academy of Engineering Physics, Mianyang, Sichuan, 621900, P. R. China 2 Presenting author vicmit@pnpi.spb.ru tel:+7(81271)30777 3 Petersburg Nuclear Physics Institute, 188300, Gatchina, Leningrad distr. Orlova Roshcha, Russia. E-mail: 1

1 INTRODUCTION CMRR under construction is a new-typed pool research reactor with light water as coolant and moderator, and Beryllium and heavy water as reflectors. The rated thermal power is 20MW. The reactor will achieve its initial criticality in 2004 with thermal and fast neutron flux 1.9x10 14 n/cm 2 s and 3.4x10 14 n/cm 2 s respectively at full power, then it will become a powerful instrument in various research fields such as nuclear physics, radioisotope production, neutron activation analysis, neutron scattering, neutron photography, and radiobiology, etc. A liquid hydrogen moderator will be located close to the reactor core to produce cold neutron to a level at which it can be transported through neutron guides into Neutron Beam Hall, where experimental facilities will be located. No bubbles, self-regulation, nice working capacity and safety are the benefit features of CNS with a sub-cooled liquid hydrogen thermosiphon. The thermosiphon between the moderator chamber and the heat exchanger makes the hydrogen at few degrees below the boiling point. Cooling helium from refrigerator removes the total heat load from CNS in the heat exchanger. CNS at CMRR is a turnkey project being designed and constructed by Petersburg Nuclear Physics Institute of Russian Academy of Science. Up to now, the conceptual design has completed, and the detail and engineering design is in progress. 2 COLD NEUTRON SOURCE AT CMRR 2.1 CNS ARRANGEMENT The CNS is placed in a vertical support tube on the top of the heavy water tank (See Figure 1). The support tube keeps the vacuum containment, which contains the thermosiphon loop. The lower part of the thermosiphon loop is the moderator chamber. The chamber contains sub-cooled liquid hydrogen without vapor due to the thermosiphon operation. Thermosiphon loop Support tube Heavy water tank Vacuum containment Reactor core Beam tube Fig 1. CNS at CMRR 2

2.2 MODERATOR CHAMBER Cylindrical moderator chamber, with 126mm outside diameter and 246mm height respectively, as the key part of CNS has a double wall construction. It consists of moderator cell, moderator cell jacket and short parts of supply tubes (See Figure 2). Hydrogen supply tubes in the chamber have inner diameter of 20 mm. The moderator chamber is made of aluminum alloy. Liquid hydrogen comes into the bottom part of the cell through the tube and spreads in the cylindrical gap. Heated hydrogen is removed by thermosiphon driving force to the outlet tube on the top of the cell. The flow of the cooling helium comes in the middle part of the chamber and spreads around the moderator cell via hole in the bottom part of the cell. Helium flow exits from the top of the chamber. Cooling helium removes the heat that is generated by reactor radiation in the chamber material. 2.3 THERMOSIPHON Fig 2. Cylindrical Moderator chamber The thermosiphon consists of four elements integrated in a loop: heat exchanger, moderator chamber and two connecting tubes (See Figure 1). Natural circulation of liquid hydrogen occurs due to a temperature difference in the loop. The cold helium from the refrigerator removes the heat from liquid hydrogen in the heat exchanger. There is a thermal balance between a heat release and a heat removal in the thermosiphon. The moderator chamber is placed at the bottom part of the thermosiphon. The shell and tube heat exchanger and the chamber connected with downward 30mm tube and upward 32mm tube. Total thermosiphon length from the bottom of the chamber to the top of the heat exchanger is 2.44 m. The lower and upper parts of the thermosiphon are made of aluminum alloy and stainless steel respectively. There are transient junctions on the tubes to connect different materials. 2.4 VACUUM CONTAINMENT The vacuum containment made of aluminum alloy is placed in the CNS support tube. The containment with 2910mm total length consists of a top flange, two tubes with different diameters and a bottom. The upper tube has inner diameter 218mm and 4mm wall thickness and the lower tube has outer diameter 144mm and 3mm wall thickness, and the bottom part has 4.5mm thickness. The upper and the lower tubes are welded together with an intermediate flange. 2.5 HYDROGEN BUFFER TANK The hydrogen buffer tank with a double wall construction is made of stainless steel. The inner 3

vessel contains gaseous hydrogen while blanketing helium is kept in the gap between the walls. There is a double wall manifold between the buffer tank and the hydrogen box. The inner vessel of the buffer tank has volume of 4m3. Hydrogen pressure in the tank and the helium pressure in the blanket are 0.25 MPa and 0.13 MPa respectively while CNS is in operation. 3 CNS PARAMETERS The liquid hydrogen thermosiphon was designed for 1000kW radiation heat load and can remove easily lower load. Taking into account heat sinks from ambient on the CNS and on the cryogenic feeding lines, reactor heating excursion and some reserve of cooling capacity, the available cryogenic capacity of the refrigerator should be 1.5 kw. Temperature difference of hydrogen in the thermosiphon legs is 2.5 K at 1 kw radiation heat load. The hydrogen flow rate is 20.8 g/s due to the driving force existing in the thermosiphon while CNS in normal operation. Hydrogen changes the temperature in the moderator chamber from 16.4 K to 18.9 K and remains in a sub-cooled state. Helium flow rate is equal to 40 g/s. Helium temperatures into the heat exchanger and after moderator cell are 14K and 18.8K respectively. Neutron spectrum and gain factors are shown in Figure3, Figure 4 and Figure 5 respectively. Liquid moderator under irradiation consists usually of the mixture of 50% para- and 50% ortho-hydrogen. 0.30 cylindrical CNS 0.25 0.20 ϕ(λ), A -1 0.15 0.10 0.05 0.00 1 10 wave-length λ, A Fig. 3 Neutron spectrum in CNS for neutrons scattered in the direction to the beam tube 4

8.0x10 10 φ(λ), cm -2 s -1 A -1 MW -1 (4π) -1 7.0x10 10 6.0x10 10 5.0x10 10 4.0x10 10 3.0x10 10 2.0x10 10 cylinder CNS 1.0x10 10 0.0 1 10 wave-length λ, A Fig. 4 Neutron brightness in CNS for neutrons scattered into the direction of C-N channel. 60 Gain factor ϕ(e)/ϕ Maxwell (E) 50 40 30 20 10 cylindrical CNS 0 0 2 4 6 8 10 12 14 16 18 20 wave-length λ, A Fig. 5 Cold neutron gain factors for CNS 5

4 CNS OPERATION AND SAFETY FEATURE 4.1 OPERATION MODE CNS system is equipped with backup cooling system to allow reactor operation at full power in case of helium refrigerator failure. Construction of the moderator chamber allows removal of radiation heat from the chamber material by warm helium flow. The cooling system supplies two operation modes for CNS: - Cold mode to keep liquid hydrogen in the moderator cell at full reactor power; - Standby mode to remove radiation heat from material when liquid hydrogen is absents in the moderator cell. The safety of the reactor and CNS operation at possible influence on each other is ensured by an independent operation for both facilities. The reactor can operate when CNS has not liquid hydrogen (CNS Standby Operation) and CNS facility can operate when reactor is shutdown. 4.2 SAFETY FEATURE The safety of the reactor is ensured by impossibility of nuclear accident in case of any breakdowns in CNS. The Vacuum Containment is designed to keep the explosion of air-hydrogen mixture. CNS facility has an inert gas blanket system for a safety reason. Helium blanket system exists for three purposes: - Insulation of hydrogen from the possible contact with air; - Monitoring of the possible hydrogen leakage; - Preventing from air penetration into the CNS containment. The well tested multiple barriers concept is fully applied to the present design. The entire moderator system is double-walled to maintain an inert gas blanket constantly monitored to provide early leak warning. In addition, the thermosiphon loop is fully contained by the Vacuum Containment, which acts as the boundary between the reactor and CNS systems. This vessel is designed to withstand explosion energy from a hypothetical hydrogen-oxygen stoichiometric explosion reaction within it. Therefore, the moderator system is isolated from the reactor core boundary by three successive passive barriers and an active constant early detection leak system between them. In consequence, although close to the core, the CNS system can be considered effectively outside the reactor system. 5 CNS UTILIZATION As cold neutrons have wavelengths comparable with the inter-atomic and intermolecular distances and energies of the same order of magnitudes as that of the thermal motion of atoms, they are ideal tools to understand the structure and arrangement of atoms. So CNS at CMRR will significantly enhances the research and development activities of the reactor. The neutron scattering experiment facility at CMRR will mainly focus in material research fields such as: - Crystallography, - Chemical physics of materials, - Surface and interfacial studies - Macromolecular and microstructure studies, - Residual stress, texture and radiography, - Neutron physics and metrology, - Irradiation. 6

Cold neutrons provided by the liquid hydrogen source are transported into the neutron beam hall, and the hall with 21.6m width x 57.6m length is located east of the reactor building (See Fig 6). Three cold neutron guides, namely C1, C2, C3 coming from CNS with 2Å, 4Å and 6Å cold neutron characteristic wavelength respectively, extend into the guide hall. After the constructions of cold neutron source system and neutron guide tube system, a few neutron spectrometers will be installed in the beam hall step by step. On the first stage, these instruments below will be installed before 2006. - Small angle neutron scattering instrument, - Reflectometer, - Trip axis spectrometer. - High intensity powder diffractometer. Helium Compressor Building Guide Hall C1 C2 C3 Neutron Guide Tunnel Reactor Hall Scattering Workshop Fig. 6 Layout of cold neutron scattering facility at CMRR 6 CONCLUSION Nice working capacity and safety are the benefit features of CNS at CMRR with a sub-cooled liquid hydrogen thermosiphon, so the CNS under construction will be the most advanced cold neutron source in the world. When the cold neutron source system and other experimental facilities are completely installed, There is not much doubt about that they will contribute to developing the state-of-the-art technology in the polymer science, biology, colloidal chemistry, metallurgy and condensed matter physics in our country. 7