Reactor steam generating heavy water

M10. Matzner, B., Experimental performance evaluation of proposed fuel elements for the steam generating heavy water reactor, NOR-1643, Columbia Univ. (1964). 

As explained in Section II, in a depressurization accident to a gas-cooled reactor (and to some water reactors, e.g., the steam generating heavy water reactor—SGHWR) there is a possibility that can temperatures might rise to about 1000 C at which point some cans could fail through their internal gas pressure. Laboratory experiments in which pre-irradiated fuel elements... 

The purpose of this section is to compare the features of the RBMK reactor operated at Chernobyl with reactor types pertinent to the UK. It will be recollected that the RBMK covers a large number of reactors and the comparisons made are indeed with Chernobyl No. 4. The UK reactors covered are in three classes the commercial reactors now built and operated or in commission (Magnox and Advanced Gas-cooled Reactor (AGR)) the prototype Steam Generating Heavy Water Reactor (SGHWR) and Prototype Fast Reactor (PFR) that have comparable performance to commercial reactors and the proposed Pressurised Water Reactor (PWR) or Sizewell B design which, it... 

Similar results on the chemical state of the corrosion products in the reactor water were reported from other BWR circuits, e. g. the reactor water of the British Steam Generating Heavy Water Reactor (SGHWR) (Bridle et al., 1986), where the insoluble iron essentially appeared as a-Fe203, containing minor amounts of Fe304. In this case, approximately 50% of the Co present in the reactor water was attached to the suspended solids, with the remainder being in a ionic dissolved state similar ratios between the particulate and the dissolved state were obtained for Co. 

One of the most frequently reported decontamination processes is the Lomi process (Low Oxidation State Metal Ions), which was originally developed by the British CEGB for removal of corrosion product deposits from the fuel bundles of the Steam Generating Heavy Water Reactor (SGHWR). Since Fe " always is the... 

Other full-system decontaminations (e. g. of the Steam Generating Heavy Water Reactor) have been performed using the Rjrco reagent or the Lomi process with and without the NP pretreatment step. The results of these operations were satisfactory as regards decontamination factors and materials compatibility at the circuit surfaces, as well as at the fuel assemblies. 

A very Important stage was reached In the development of the Steam Generating Heavy Water Reactor system when the 100 MWe prototype reactor at Winfrith was successfully commissioned at the end of I967. 

MCMILLAN R.N.H., O DELL P.P. and WRAY D. The physics and control of the Steam Generating Heavy Water Reactor. 

SYNOPSIS This paper describes the bases for control of steam generating heavy water reactor stations and gives some detail of the system adopted for the Winfrith SGHWR. 

Development of zirconium alloy pressure tubes for the Winfrith Heath Steam Generating Heavy Water Reactor, Inst, of Mech. Eng. Conf. on New Engineering Mats., 13th-l4th October, 1965. 

The Steam Generating Heavy Water Reactor is the first in a new line of development as far as the UKAEA is concerned, and while it has certain factors in common with other water-cooled reactors such as the American BWRs and the Canadian NPD-CANDU series, some aspects of its technology represent a departure from previous practice. 

We have heard papers describing the British Steam Generating Heavy Water Reactors in some detail and have had the benefit of having a series of review papers from organizations in other countries engaged on the construction of heavy water reactors for power generation. These papers have described the present position and the prospects for the future. 

The second area was the major research and development centre, based at the Atomic Energy Research Establishment, Harwell. This too expanded with various offshoots the reactor division was moved to Winfrith in Dorset. As well as many research reactors, Winfrith would also be home to the high-temperature reactor DRAGON project and the steam generating heavy water reactor (SGHWR). 

TNA PRO EG 12/67. Thermal Reactor Working Party Study Task 3 economics of High Temperature Reactors (HTRs) and Steam Generating Heavy Water Reactors (SGHWRs). JG Liverman to Vintner, 29 November 1971. 

Although LEO had been dropped from the programme, work on various forms of water reactor did not stop. A variety of studies were continued into various other esoteric forms of water-cooled reactor, for example, the steam cooled heavy water reactor (SCHWR) or the steam generating heavy water reactor (SGHWR). Meanwhile, the Canadians continued to build on their wartime work on heavy water, and had produced a design for a reactor using natural uranium and heavy water. This design was known as the CANDU (Canada deuterium uranium) reactor. 

TNA PRO AB 17/105. The Winfrith SGHWR. This AEA publication gives a full description of the Winfrith station. See also TNA PRO AB 17/93. Steam Generating Heavy Water Reactor. TNA PRO AB 17/220. Britain s SGHWR. TNA PRO EG 7/38. Steam Generating Heavy Water Reactor (SGHWR) programme. 

TNA PRO EG 7/39. Steam Generating Heavy Water Reactor (SGHWR) programme. The SGHW Prototype Reactor. A Firth, N Bradley and JER Holmes, 1963. 

TNA PRO EG 1/363. Prototype Steam Generating Heavy Water Reactor (SGHWR). SGHWR for North of Scotland Hydro-Electricity Board. St. Clair C Hood, UKAEA, to G Hubbard, Ministry of Technology, 11 August 1967. TNA PRO AB 65/869. Stake Ness tender assessment. 

TNA PRO EG 7/93. Steam Generating Heavy Water Reactors (SGHWR) sale to Scotland. MI Michaels (Ministry of Technology) to Sir Charles Cunningham (UKAEA), 8 October 1970. 

TNA PRO EG 12/134. Specific proposals for Steam Generating Heavy Water Reactor (SGHWR) and High Temperature Reactor (HTR) development. Status of SGHWR with Particular Reference to Safety. The Nuclear Power Group Limited, British Nuclear Design and Construction Limited, November 1973. Thermal Reactor Policy, House of Commons Debate (Fifth series), 25 January 1978, Vol. 942, cc. 1391-1392. 

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